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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
. ~ - . .- - - ._ . _ _ . -- -. .. .
g - .5 ~J Ctation Support Department
& 10CFR50.90
^
v PECO NUCLEAR ecco see,2, cemne,x 965 Chesterbrook Boulevard A Unit of PECO Energy Wayne, PA 190874691 February 25,1997 Docket Nos. 50-352 50453 5
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. 96-06-0 Company Name Change Gentlemen:
PECO Energy Company (PECO Energy) is submitting Technical Specifications (TS) Change Request No.96-064, in accordance with 10CFR50.90, requesting a change to the Umerick Generating Station (LGS) Unit 1 and Unit 2 Facility Operating Ucenses (FOLs), and Appendix B of the licenses (i.e., Environmental Protection Plan (EPP)), reflecting a corporate name change from Philadelphia Electric Company to PECO Energy Company. In addition, we are requesting changes to the LGS Units 1 and 2, FOL, and Appendix A (i.e., TS) of the licenses which will remove obsolete information and correct typographical errors.
Information supporting these changes is contained in Attachment 1 to this letter, and copies of the " marked-up" license pages are contained in Attachment 2. This information is hing submitted under affirmation, and the required affidavit is enclosed.
We request that if approved, the changes be issued by August 1,1997, and become effective within 30 days of issuance.
If you have any questions, please do not hesitate to contact us.
Very truly yours,
.h
Director - Ucensing Attachments Enclosure cc: H. J. Miller, Administrator, Region I, USNRC (w/ attachment, enclosure)
N. S. Perry, USNRC Senior Resident inspector, LGS (w/ attachment, enclosure) ,
i R. R. Janati, PA Bureau of Radiation Protection (w/ attachment, enclosure)
I i
9703050046 970225 PDR ADOCK 05000352 r %Q h
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p , PDR 4
.N ,.
r COMMONWEALTH OF PENNSYLVANIA - : ]
- ss '
COUNTY OF CHESTER :
l l
D. B. Fetters, 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 j Technical Specifications Change Request No. 96-06-0 " Company Name Change," for
, Limerick Generating Station, Unit 1 and Unit 2, Facility Operating Ucense 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. I i
N k A W >
1 Subscribed and sworn to 4
before me thiqdhay of 997.
j 0
Notary Public E Nov ,eal I g 999
j l .
l l
l P
ATTACHMENT 1 LIMERICK GENERATING STATION l UNITS 1 AND 2 l
DOCKET NOS.
50-352 50-353 I
UCENSE NOS.
NPF-39 NPF-85
" COMPANY NAME CHANGE" Information Supporting Changes - 8 Pages
+
Dockst Nos.50-35x 50-353 License Nos. NPF-39 NPF-85 DISCUSSION AND DESCRIPTION OF THE PROPOSED CHANGES PECO Energy Company (PECO Energy) is requesting Ucense changes which will reflect a name change from Philadelphia Electric Company to PECO Energy Company.
The name change will alter the LGS Unit 1 and Unit 2 Facility Operating Licenses (FOls), and Appendix B of the licenses (i.e., Environmental Protection Plan (EPP)). In
, addition, correction of typographical errors and elimination of obsolete information l from the LGS Unit 1 and Unit 2 Facility Operating Ucenses (FOLs), and Appendix A l (i.e., Technical Specifications (TS)) of each license is requested.
I TS SAFETY ASSESSMENT !
1 l The following changes and information supporting each change is provided.
NAME CHANGE l Change 1 in a letter dated December 21,1993, the Philadelphia Electric Company (i.e., the :
I licensee) informed the NRC that it was officially changing it's name to PECO Energy l Company effective January 1,1994. PECO Energy Company is not a new l corporation, or a successor corporation to Philadelphia Electric Company, but remained and continues to be tae same company with a different name. As a result, i contracts, agreements, obligations, licenses and permits relating to Philadelphia -
Electric Company continue to be legal, valid, and binding with respect to PECO l Energy Company. This proposed change is editorial in nature and is necessary to .
l ensure that the name on the LGS licenses corresponds to the company's new name. l Change 2 !
TS Administrative Controls Section 6.5.2.2 requires that members of the Nuclear Review Board (NRB) be appointed in writing by the Senior Vice President and Chief l Nuclear Officer. PECO Energy recently established the position and title of President and Chief Nuclear Officer as the ranking officer of our Nuclear Business Unit.
Therefore, in order to retain the same level of authority, Section 6.5.2.2 will be revised to eliminate the words Senior Vice President. Chief Nuclear Officer will be retained and will designate the ranking authority in the Nuclear Unit for NRB appointments.
TYPOGRAPHICAL ERRORS Chance 3 Unit 1 FOL, Section 2.E. contains a spelling error involving the word " Safeguards."
This proposed change corrects the spelling error.
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Docket Nos. 50-352 50-353 Ucense Nos. NPF-39 NPF-85 l
Chanae 4 Unit 1 and Unit 2 TS Index, page x, contains reference to Table 3.3.7.9.1 " Fire -
Detection Instrumentation." This Table was removed from Unit 1 and Unit 2 TS by letter from the NRC dated November 20,1995, reflecting amendment numbers 104 and 68, respectively. The index reference to the Table was inadvertently overlooked, and no longer applies; therefore, it is proposed that it be deleted. :
Change 5 '
Unit-1 and Unit 2 TS Bases Index, page xix, contains reference to Bases Section 3/4.3.8 " Turbine Overspeed Protection System." This Bases Section was removed from Unit 1 and Unit 2 TS by letter from the NRC dated August 24,1995, reflecting amendment numbers 100 and 64, respectively. The Bases Index was inadvertently overlooked, and no longer applies; therefore, it is proposed to be deleted. l ChanaeJ ,
Unit 1 and Unit 2 TS page 3/4 3-8 " Table 4.3.1.1-1" contains typographical and unit I consistency errors. The Unit 1-TS's Table, column four, " CHANNEL CAllBRATION," is missing the footnote annotation (a). Unit 1 and Unit 2 TS's Table, footnote (b) reads
" to overlap for a least 1/2 decades..." however, the footnote should read "...to overlap for at least 1/2 decades..." These proposed changes will correct the noted j errors.
Chance 7 Unit 2 TS page 3/4 6-14 " Containment Systems, Surveillance Requirements (SR)," SR 4.6.2.1.e. contains a typographicai error not consistent with Unit 1. To be consistent the word " calculation" should be changed to " calculated." This requirement was amended for Unit 1 and Unit 2 TS by letter from the NRC dated January 25,1996, reflecting amendment numbers 108 and 71, respectively. The tense of the word was inadvertently in error; therefore, it is proposed to be corrected.
Change 8 Unit 1 and Unit 2 TS page 3/4 6-42 " Table 3.6.3-1 Notation," note 20. contains reference to the MSIV-LCS (Main Steam isolation Valve - Leakage Control System).
This system was physically removed, and therefore removed from Unit 1 Md Unit 2 TS by letters from the NRC dated January 25,1996 and February 16,1995, reliecting amendment numbers 107 and 53, respectively. The note reference was inadvertently l overlooked, no longer applies, and therefore is proposed to be deleted. !
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Docket Nos. 50-352 50-353 Ucense Nos. NPF-39 I i
NPF-85 Chance 9 Unit 1 and Unit 2 TS page 3/4 6-43 " Table 3.6.3-1 Notation," note 33. contains reference to the Secondary Containment isolation Valve Tables 3.6.5.2.1-1, and !
3.6.5.2.2-1. These Tables were removed from Unit 1 and Unit 2 TS by letter from the i NRC dated November 20,1995, reflecting amendment numbers 105 and 69, l respectively. The note reference was inadvertently overlooked and no longer applies; therefore, it is proposed to be deleted.
Chance 10 I Unit 1 TS page 3/4 8-15 " Electrical Power Systems" contains a typographical error.
Umiting Condition For Operation (LCO) 3.8.3.1 a. 2. states " Unit 2 Division 2, Consisting of:" the LCO should read " Unit 1 Division 2, Consisting of:" The unit I designation error occurred during processing of amendment number 24, which was issued June 15,1989. This proposed change will correct the noted unit error.
Change 11 Unit 1 and Unit 2 TS page 6-8 " Administrative Controls" Section 6.5.1.6 contains a typographical error. Responsibilities Section 6.5.1.6 "The PROC shall be responsible for:" should read "The PORC shall be responsible for:" This proposed change will correct the wording error.
Change 12 ;
Unit 1 and Unit 2 TG page 3/4 3-103 "Offgas Gas Monitoring Instrumentation," Action i
- b. requires that an explanation be submitted to the NRC in the next Semiannual Radioactive Effluent Release Report. The frequency for submitting the report was changed from semiannual to annual by letter from the NRC dated August 10,1994, reflecting amendment numbers 73 and 35 for Unit 1 and Unit 2, respectively. The reference to the semiannual frequency was overlooked, and therefore is being i i
changed to reflect the annual frequency.
OBSOLETE REQUIREMENTS Change 13 ,
Unit 1 FOL, Section 2.C.(4), references a requirement pertaining to Qualification of '
Personnel for a Unit 1 low power license. This requirement was fulfilled and documented in the LGS SER (NUREG-0991 Safety Evaluation Report related to the operation of Umerick Generating Station, Units 1 and 2, dated August 1983),
Supplement 4, issued May 1985. Therefore, this requirement of the Ucense is rio longer necessary.
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Dock @t Nos. 50-352 50-353 License Nos. NPF-39 NPF-85 Chance 14 Unit _1 FOL, Section 2.C.(5), references a requirement pertaining to ensuring operability of the Emergency Response Capabilities Safety Parameter Display within 30 days after the completion of the 100-Hour Warranty Run. This requirement was fulfilled and documented in the LGS SER, Supplement 8, issued June 1989. Therefore, this requirement of the License is no longer necessary.
. Chance 15 Unit 1 FOL, Section 2.C.(6), references a requirement pertaining to Post-Fuel Loading initial Test Program. This requirement was fulfilled and documented in the LGS SER, Supplement 8, issued June 1989. Therefore, this requirement of the License is no longer necessary.
Chance 16 Unit 1 FOL, Section 2.C.(7), references a requirement pertaining to the submittal of the inservice inspection Program. This requirement was fulfilled and documented in the LGS SER, Supplement 7, issued April 1989. Therefore, this requirement of the Ucense is no longer necessary.
Chance 17 Unit 1 FOL, Section 2.C.(8), references a requirement pertaining to implementation of commitments applicable to Generic Letter 83-28 " Salem ATWS Event." This requirement was fulfilled and documented in the LGS SER, Supplement 2, issued October 1984, Supplement 8, issued June 1989, and Supplement 9, issued August 1989. Therefore, this requirement of the License is no longer necessary.
Chance 18 Unit 1 FCL, Section 2.C.(9), references a requirement pertaining to submittal of a turbine system maintenance program. This requirement was fulfilled and documented in the LGS SER, Supplement 8, issued June 1989. Therefore, this requirement of the '
Ucense is no longer necessary.
Chance 19 -
Unit 1 FOL, Section 2.C.(12), references a requirement pertaining to modifications to the Remote Shutdown System prior to startup following the first refueling outage. This requirement was fulfilled and documented in the LGS SER, Supplement 8, issued June 1989. Therefore, th:s requirement of the Ucense is no longer necessary.
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Docket Nos. 50-352 !
50-353 !
Ucense Nos. NPF-39 -
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! NPF-85 h
l l Chance 20
- Unit 1 FOL, Section 2.C.(14), references a requirement pertaining to connection of the .
Refueling Floor Volume to the Standby Gas Treatment System. This requirement was l fulfilled and documented in the LGS SER, Supplement 7, issued April 1989. Therefore, this requirement of the License is no longer necessary.
J Chanae 21 4
Unit 1 FOL, Section 2.C.(15), references a notice pertaining to the potential event that the NRC would find a lack of progress in completion of the Emergency Planning Procedures, which would be subject to 44 CFR Part 350. This notme was not necessary since LGS achieved and maintained an adequate state of emergency i preparedness; therefore, this requirement of the License is no longer necessary.
- Change 22
- Unit 1 FOL, Section 2.D.(a), references an exemption pertaining to the General Design
! Criteria (GDC) 61, and the Standby Gas Treatment System operation during the first i refueling outage. The time period for this exemption has passed; therefore, this
- . reference in the License is no longer necessary.
Chance 23
- Unit 1 FOL, Section 2.D.(b), references an exemption pertaining to GDC 56, and the
- requirement for additional automatic isolation prior to startup following the first i
refueling outage. This requirement was fulfilled and documented in the LGS SER, Supplement 8, issued June 1989. Therefore, this reference contained in the Ucense is no longer necessary.
Chance 24 - l I
Unit 1 FOL, Section 2.D.(c), references an exemption pertaining to GDC 19, and condition of requiring modifications to the Remote Shutdown System. This
- requirement was fulfilled and documented in the LGS SER, Supplement 8, issued June
! 1989. Therefore, this reference contained in the Ucense is no longer necessary.
j Chanae 25 l Unit 1 FOL, Section 2.D.(g), references a one-time exemption pertaining to the !
l; performance of local leak rate testing at the first refueling outage. This exemption was I j documented in the LGS SER. The time period for this exemption has passed; therefore, this reference in the License is no longer necessary.
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Docket Nos. 50-352 i 50-353 I
License Nos. NPF-39 NPF-85 i
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l Chanae 26
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Unit 1 FOL, Section 2.D.(h), references a one-time exemption pertaining to inerting of )
containment six months after initial criticality. This exemption was documented in the LGS SER, Supplement 5, issued July 1985. Unit 2 FOL, Section 2.D.(e), references a one-time exemption pertaining to inerting of containment six months after initial criticality. This exemption was documented in the LGS SER, Supplement 9, issued August 1989. The time periods for these exemptions have passed; thersfore, these references in the License are no longer necessary.
Chance 27 Unit 1 FOL, Section 2.D.(i), references an exemption pertaining to conduct of a full participation emergency preparedness exercise within one year before issuance of a
. full power license. This exemption was documented in the LGS SER, Supplement 6, August,1985. The time period for this exemption has passed; therefore, this reference in the License is no longer necessary.
Change 28
- Unit 1 and Unit 2 TS pages 3/4 5-1,3/4 5-2,3/4 6-15,3/4 6-16,3/4 7-1, and 3/4 7-3 contain reference, by means of a footnote, to a one-time (i.e., temporary) change affecting the Allowed Outage Times (AOT) for Emergency Service Water, Residual Heat Removal Service Water, Residual Heat Removal and Core Spray Systems. Unit 1 TS amendment number 86 issued on January 27,1995, and Unit 2 TS amendment number 70 issued on November 30,1995 incorporated the footnotes. This allowance was necessary to perform modifications to the systems and was permitted'one time during the Unit 2 third refueling outage (i.e., January 1995) and one-time during the Unit 1 sixth refueling outage (i.e., January 1996). Since the modifications are complete on both units and the time period for this allowance has passed, these references in TS are no longer necessary.
Change 29 Unit 2 FOL, Section 2.D, references an exemption from criticality monitoring requirements of 10CFR 70.24. By letter dated November 22,1988, the NRC authorized materials license SNM-1977 and an amendment to Construction Permit No.
CPPR-107. The material license and amendment were effective until they were superseded by the LGS, Unit 2, operating license under 10CFR Part 50, or by an expiration date of December 31,1992. These limitations were contained in the i November 22,1988 letter from the NRC, and in the materials license. The Unit 2 operating license was issued on August 25,1989, thereby nullifying SNM-1977. This change will eliminate the obsolete exemption.
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Docket Nos. 50-352 50-353 License Nos. NPF-39 NPF-85 INFORMATION SUPPORTING A FINDING OF NO SIGNIFICANT HAZARDS CONSIDERATION PECO Energy Company has concluded that the proposed changes to the Umerick Generating Station Unit 1 and Unit 2 licenses, which will reflect the new company name, eliminate obsolete information, and correct typographical errors, do not involve a Significant Hazards Consideration. The editorial changes resulting from the company name change, typographical errors and obsolete requirements do not change or delete existing requirements contained in TS, which were not previously approved by the NRC or were time dependent, whereas they are now obsolete. Therefore, these changes to the FOL, the TS and the EPP will not potentially adversely imnact accidents previously evaluated in the SAR. In support of this determination, an evaluation of each of three standards set forth in 10CFR50.92 is provided below. j
- 1. The orooosed TS changes do not involve a sianificant increase in the orobability !
or conseauences of an accident oreviousiv evaluated.
The company name change and typographical corrections are editorial and will not alter the operation of equipment assumed to be an initiator of any analyzed event or transients previously evaluated. The license provisions were i satisfactorily completed, and as such, have no effect on any previously l evaluated accident scenario. The changes will not alter the operation of '
equipment assumed to be available for the mitigation of accidents or transients, l nor will they alter the operation of equipment important to safety previously evaluated.
Therefore, the changes do not involve a significant increase in the probability or consequences of an accident previously evaluated.
- 2. The prooosed TS changes do not create the oossibility of a new or different kind of accident from any accident oreviousiv evaluated.
The company name change and typographical corrections are editorial and will not involve any physical changes to the plant systems, structures, or components. The license provisions were satisfactorily completed, and as
. such, have no effect on any previously evaluated accident scenario. The proposed changes do not allow plant operation in any mode that is not already evaluated. The changes will not alter the operation of equipment important to safety previous!y evaluated.
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Docket Nos. 50-352 50-353 Ucense Nos. NPF-39 NPF-85 Therefore, the changes do not create the possibility of a new or different kind of accident from any accident previously evaluated.
- 3. The oronosed TS changes do not involve a significant reduction in a margin of safetv.
The company name change and typographical corrections are editorial and will not affect the manner in which the facility is operated, or change equipment or features which affect the operational characteristics of the facility. There is no margin of safety as defined in the bases of any TS regarding the name of the company, or affected by the corrections or deletion of obsolete license provisions. l Therefore, these proposed changes do not involve a significant reduction in a j margin of safety. ;
INFORMATION SUPPORTING AN ENVIRONMENTAL ASSESSMENT !
i An Environmental Assessment is not required for the license (i.e., FOL, TS, and EPP) changes proposed by this request because the requested changes to the Limerick Generating Station, Unit 1 and Unit 2 licenses conform to the criteria for " actions eligible for categorical exclusion," as specified in 10 CFR 51.22(c)(9). 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 types or significant increase in the amounts of any effluent that may be released off-site. In addition, the proposed changes do not involve a significant increase in individual or cumulative occupational radiation exposure.
CONCLUSION The Plant Operations Review Committee and the Nuclear Review Board have reviewed these proposed changes to the Limerick Generating Station, Unit 1 and Unit 2, licenses and appendices, 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.
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