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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
i,. 10 CFR 50.90 -[
PHILADELPHIA ELECTRIC COMPANY ,
NUCLEAR GROUP HEADQUARTERS l 955-65 CHESTERBROOK BLVD. !
i WAYNE, PA 19087 5691 (u si sao soco July 13, 1990 Docket Nos. 50-352 50-353 :
License Nos. NPF-39 l NPF-85 i l
U.S. Nuclear Regulatory Commission Attn: Document Control Desk
. Washington, DC 20555 '
SUBJECT:
Limerick Generating Station Units 1 and 2 Technical Specifications Change Request '
Dear Sir:
Philadelphia Electric Company hereby submits Technical Specifications Change Pequest No. 89-15-0 in accordance with 10 CFR 50.90. requesting an amendment I
.totheTechnicalSpecifications(TS)(AppendixA)ofOperatingLicenseNos.NPF-39 ;
and NPF-85. Information supporting this Change Request is contained in Attachment 1 l to this letter, and the proposed replacement pages are contained in Attachment 2.
This submittal requests changes to TS Section 6.0, including the addition Lof a new TS Section 6.5.3, to reflect the implementation of a Station Qualified t l Reviewer (SQR) Program for review and approval of new station programs, procedures.
and changes thereto.
p If you have any questions regarding this matter, please contact us.
l !
/ Very truly yours.
N
.26 M G. A. unger, Jr. / '
Manager e Licensing Section ,
Nuclear Engineering and Services 9007180245 900713 PDR ADOCK 05000352 .;
P PDC '
Attachments cc: ,T. T. Martin, Administrator, Region I. USNRC 00 T. J. Kenny,~USNRC Senior Resident inspector, LGS
.T. M. G,erusky, Director, PA Bureau of Radiological Protection iIk [
. 30
L
< i ,
COMMONilEALTH OF PENNSYLVANIA S 4
- ss.
COUNTY OF CHESTER :
D. R. Helwig, being first duly. sworn, deposes and says:
That he is Vice President of Philadelphia Electric Company; the Applicant hereint that he has read the foregoing Application for o - Amendment of Facility Operating License Nos. NPF-39 and NPF-85 (Technical Specifications Change Request No. 89-15) to reflect the implementation of a Station Qualified Reviewt' Program, 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.
)%
Vice Preside P
Subscribed and sworn to
beforeme.this13Tay of ,>d ,1990.
y fet/mNs d. "h t wdn i Notary Public CATHERN E E2 Nothry Pubhc JCJ32:rLSTka
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ATTACHMENT 1 L.
L LIMERICK GENERATING STATION
..f m< Units 1 and 2-Il, ,- :
. Docket Nos. .50-352-1e- 353 te License Nos.'NPF-39 NPF-85 e
LTECHNICAL SPECIFICATIONS CHANGE REQUEST
- " Station Qualified Reviewer ~ Program" Supporting information for Changes 6 pages y.
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Docket NCs. 50-352 a'
50-353 License Not. NPF-39 ,
NPF-85 l
l l
Philadelphia _ Electric Company (PECo), Licensee under Facility Operating Licenses HPF-39 and NPF-85 for Limerick Generating Station (LGS), Units 1 and 2. respectively, i lereby requests that'the Technical Specifications (TS) contained in Appendix A of the Operating Licenses be amended as proposed herein to reflect the implementation of a Station Qualified Reviewer (SQR) Program for the review and approval of new programs, procedures, and changes thereto at LGS. The proposed changes are indicated by a i vertical bar in the margin of pages xxvii (INDEX), 6-8. 6-12, 6-12a (new page), 6-13 and 6-19 for both LGS Unit I and Unit 2 TS, and are contained in Attachment 2.
t We request the changes proposed herein to be Jffective upon issuance of the Amendments. '
This 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 Changes TheStationQualifiedReviewer(SQR)Programisaprogram/proceduralreviewand approval process using qualified reviewers to perform a review and designated ;
Superintendents for approval of new programs, procedures, and changes thereto. This program has been approved by the NRC for the Public Service Electric and Gas (PSE&G)
Company facilities. There are two key areas of importance under the SQR program.
The Plant Operations Review Comm?ttee (PORC) will no longer be required to render a determination as to whether or not a new program. procedure, or change thereto constitutes an unreviewed safety question (USQ) in accordance with 10 CFR 5C.59, i PORC will no longer be required to review and recommend approval / disapproval of new programs or program changes and certain types ;
of procedures or procedure changes to the Plant Manager. ;
l'
' t l The responsibility and authority to perform these functions will be transferred to responsible Superintendents designated by the Plant Manager. .
A brief description of how this program will be implemented at LGS is provided below.
1 i
o The PORC Chairman approves plant personnel recommended to be Station I Qualified Reviewers (SQRs) for specific types of programs and classes of .
L' procedures. The SQR will be an individual knowledgeable in the functional area affected and may be from the same organization, but who is not the individual preparer.
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1 a * .
Docket Nos. 50-352 50-353 i 1
License Nos. NPF-39 i NPF-85 o The Plant Manager, as authorized by Administrative Procedures, appoints l plant Superintendents to be responsible for approving specific types of ;
programs and classes of procedures. The appointed Superintendent will be the individual responsible for and cognizant of the affected functional area.
o Each new program, procedure, or change thereto is reviewed by the designated SQR. The SQR determines when a cross-disciplinary review by .
other personnel is necessary prior to ap roval. The new program. '
procedure, or change thereto and accompanying 10 CFR 50.59 Review ,
documentation (i.e.,evaluationoftheproposedchange,newprocedureor '
new program in accordance with 10 CFR 50.59) is reviewed by the. :
responsible Superintendent, including a determination as to whether a 10 CFR 50.59 safety evaluation is required or not. If not, the new program, '
procedure, or change thereto is then approved by the responsible Superintendent or the Plant M eager. If a 10 CFR 50.59 safety evaluation is required, the entire new progism, procedure, or change package, including the 10 CFR 50.59 safety evaluation, is reviewed by PORC.
o- PORC continues to be responsible for the review and recommendation for '
approval / disapproval of Administrative Procedures, and any new program, procedure, or change thereto that requires an unreviewed safety question >
determination (i.e.,10CFR50.59safetyevaluation)beperformed, o The Plant Manager continues to be responsible for the approval of 4 Admi11strative Procedures. Security Plan Implementing Procedures.
Emergency Plan implementing Procedures, and any new program, procedure, or change thereto that requires an unreviewed safety question determination
, (i.e., 10 CFR 50.59 safety evaluation) be performed.
I !
o Temporary procedure changes (TPCs) will be implemented as before, however, the TPC will be reviewed by the designated SQR (including a cross- ,
disciplinary review, if necessary) and approved by the Plant Manager or '
' responsible Superintendent, as appropriate, within 14 days of implementation.
i 1
L 1mplementing the SQR Program at LGS, Units 1 and 2 will involve the proposed TS changes described below. All changes are reflected in the unit specific TS pages y contained in Attachment 2. !
- 1. . '
Revise TS Section 6.5.1.6.a to read " Review of (1) Administrative Procedures and changes thereto, (2) ner programs or procedures required by Specification 6.8 and requiring a 10 CFR 50.59 safety evaluation, and (3) proposed changes to programs or procedures required by Specification 6.8 and requiring a 10 CFR 50.59 safety evaluation;" to indicate the reduction l
in the scope of PORC's program / procedural review. -
k 1
i: l r '
Docket Nos. 50-352
. SC 353 !
License Nos. HPF-39 I NPF-85 j s
- 2. . Revise TS Section 6.5.1.6.e to read " DELETED." The new provisions added !
under. item #4 below will require PORC to review 10 CFR 50.59. safety !
evaluations for those new procedures and changes to existing procedures for which a 10 CFR 50.59 safety evaluation is prepared as part of the l overall new procedure or procedure change package. Therefore, the ;
requirement for PORC to review 10 CFR 50.59 safety evaluations associated ;
with procedures and changes thereto can be deleted. ;
- 3. Change the reference to TS Section "6.5.1.6a" under TS Section 6.5.1.7b to' ,
read "6.5.1.6b" to indicate that PORC will no longer be responsible for +
rendering determinations in writing with regard to whether or not new ,
programs, procedures, or changes thereto constitute an unreviewed safety :
question. The responsibility and authority for this function is !
transferred to the responsible Superintendent under the SQR program.
- 4. Add the following new TS section to specify the basic requirements of the SQR program.
"6.5.3 PROGRAM / PROCEDURE REVIEW AND APPROVAL All programs and procedures required by Specification 6.8 shall be reviewed and approved as described below. ,
l 6.5.3.1 Each new program, procedure, or change thereto shall be '
independently reviewed by a Station Qualified Reviewer (SQR) who is knowledgeable in the functional area affected but is not the individual preparer. The SQR may be from the same organization as the preparer. The ,
SQR shall render a determination in writing of whether or not cross-disciplinary review of a new program, procedure, or change thereto is #
l necessary. If necessary, such review shall be performed by appropriate I
personnel.
6.5.3.2 Each new program, procedure, or change thereto shall be reviewed
=by the Superintendent designated by Administrative Procedures as the responsible Superintendent for that program or procedure, and the review shall include a determination of whether or not a 10 CFR 50.59 safety evaluation is required. If a 10 CFR 50.59 safety evaluation is not i required, the new program, procedure, or change thereto shall be approved by the rtisponsible Superintendent or the Plant Manager prior to I
i implementation. Administrative Procedures shall be reviewed by PORC prior ,
to approval. Administrative Procedures, Security Plan Implementing l
Procedures, and Emergency Plan Implementing Procedures shall be approved by the Plant Manager or his designated alternate in accordance with Specification 6.1.1.
! 6.5.3.3 If the responsible Superintendent determines that a new program, l procedure, or change thereto requires a 10 CFR 50.59 safety evaluation, l.
the responsible Superintendent shall render a determination in writing of whether or not the new program, procedure, or change thereto involves an unreviewed safety question (USQ), and shall forward the new program, .
procedure, or change thereto with the associated safety evaluation to PORC for review. If an USQ is involved, NRC approval is required by 10 CFR 50.59 prior to implementation of the new program, procedure, or change.
Docket Nos.
50-352 e
50-353 ,
License Nos. NPF-39 i NPF-85 j l
6.5.3.4 Personnel recommended to be SQR$ shall be approved and designated j as such by the PORC Chairman. The responsible Superintendents shall i ensure that a sufficient complement of SQRs for their functional area is I maintained in accordance with Administ'ative Procedures, j l
6.5.3.5 Temporary procedure changes shall be reviewed and approved in j accordance with Specification 6.8.3.
l i
6.5.3.6 Records documenting the activities performed under Specifications l 6.5.3.1 through 6.5.3.5 shall be maintained in accordance with ;
Specification 6.10." i l
- 5. Revise TS Section 6.8.2 to read "6.8.2 Each procedure of Specification i 6.8.1, and changes thereto, and any other procedure or procedure change i that the Plant Manager determines to affect nuclear safety, shall be l reviewed and approved in accordance with Specifications 6.5.1.6. 6.5.1.7 '
and/or 6.5.3, as appropriate, prior to implen,entation. Each procedure of l Specification 6.8.1 shall also be reviewed periodically as set forth in Administrative Procedures," to indicate that procedural review and l approval will be in accordance with the appropriate TS Sections. ,
- 6. Revise TS Section 6.8.3.c to read "The change is documented, reviewed by ;
an SQR in accordance with Specification 6.5.3.1, and approved by either t the Plant Manager or his designated alternate in accordance with Specification 6.1.1, or the Superintendent designated by Administrative Procedures as the responsible Superintendent for that procedure within 14 days of '
lementation." to make the review and approval process for TPCs ,
consists with that for permanent procedure changes. This TS change provides f or a cross-disciplinary review, if necessary, and maintains the same level of management approval, a
- 7. Revise IS Section 6.10.2.e to read " Records of changes made to the programs and procedures required by Specification 6.8." to require a five ,
year retention period for records of changes made to programs as a result i of the SQR activities conducted in accordance with proposed Specification 6.5.3, and maintain consistency between the requirements of Specification >
L s
6.10 and proposed Specification 6.5.3.6.
- 8. Add "6.5.3 PROGRAM / PROCEDURE REVIEW AND APPROVAL 6-12" to page xxvii of the Index to indicate the addition of TS Section 6.5.3, and revise the 1
page numbers for TS Sections 6.6 and 6.7 from "6-12" to "6-12a" due to relocation of these requirements to the new proposed page.
s
1 Docket Nos. 5f-352 ,
5)-353 i
License Nos. NPF-39 NPF-85 Safety Assessment The proposed changes are administrative in nature. The institution of the SQR Program will help to streamline PORC ectivities and improve the effectiveness of PORC reviews by making more efficient use of technical expertise available. There are no changes to plant equipment, plant design, limiting safety sys%n settings, or plant system operation. New programs, procedures, and ches:; inereto will be reviewed by qualified personnel designated by the PORC Chairman and knowledgeable in the affected functional area. The program will be controlled by Administrative Procedures which will continue to be reviewed by PORC and approved by the Plant Manager. PORC will continue to review those new programs, procedures, and changes thereto for which an unreviewed safety question determination (i.e., 10 CFR 50.59 safety evaluation) is required to be performed. As a result, the proposed administrative changes will not ,
decrease the safety oversight function which PORC performs.
Information Supporting a finding of No Significant Hazards Consideration We have concluded that the proposed changes to the LGS TS, which reflect the implementation of a Station Qualified Reviewer Program, do not constitute a Significant Hazards Consideration. In support of this determination, an evaluation of each of the three standards set forth in 10 CFR 50.92 is provided below.
- 1) _The proposed changes do not involve a significant increase in the probability or consequences of an accident previously evaluated.
The proposed changes are administrative changes which implement a program / procedural review and approval process through the use of qualified personnel designated by the PORC Chairman for review purposes and Superintendents designated by the Plant Manager, as authorized by Administrative Procedures, for approval of specific types of programs and classes of procedures. The SQR will be required to consider, document, and implement a cross-disciplinary review prior to approval, if necessary. The program will be controlled by Administrative Procedures which will continue to be reviewed by PORC and approved by the Plant Manager. PORC will continue to review those new programs, procedures, and changes thereto for which an unreviewed safety question determination (i.e., 10 CFR 50.59 saf y evaluation) is required to be performed. As a result, the proposed administrative changes will not decrease the safety oversight function which PORC performs. The proposed changes will add more detailed requirements regarding program / procedure review and approval to the TS which will strengthen the controls over this process. The proposed changes do not affect any plant hardware, plant design, limiting safety system settings, or plant systems, and therefore, do not modify or add any initiating parameters that would cause a significant increase in the probability or consequences of any accident previously evaluated.
- 2) The proposed changes do not create the possibility of a new or different kind of l accident from any accident previously evaluated.
l The proposed changes will implement a program / procedural review and approval l process and are administrative in nature. The program will be controlled by Administrative Procedures which will continue to be reviewed by PORC and approved by the Plant Manager. PORC will continue to review those new programs, procedures, and changes thereto for which an unreviewed safety question determination (i.e., 10 CFR 50.59 safety evaluation) is required to be
' + i Docket Nos. 50-352 e*
50-353 !
License Nos. NPf-39 NPF-85 performed. As a result, the proposed administrative changes will not decrease the safety oversight function which PORC performs. The proposed changes do not involve any physical alterations of plant configuration, changes to setpoints, or operating parameters, nor do they involve any potential initiating events that would create the possibility of a new or different kind of accident from '
any accident previous'y evaluated. ,
i (3) _The proposed changes do not involve a significant reduction in a margin of safety, i
The proposed changes are administrative in nature and involve only the transfer of responsibilities and authority for program / procedural review and approval to responsible Superintendents. PORC will continue to review and the Plant Manager will continue to approve those new programs, procedures, and changes thereto for which an unreviewed safety question determination (i.e., 10 CFR 50.59 safety evaluation) is required to be performed. Accordingly, the same management level >
of review and approval of new programs, procedures, and changes thereto as currently required by TS is maintained. That is, the responsible Superintendents are also PORC members. Therefore, the margin of safety is not reduced. The proposed changes do not impact plant systems or operations and, i therefore, do not involve a significant reduction in a margin of st fety.
Information Supportina an Environmental Assessment An environmental assessment is not required for the changes proposed by this Change Request because the requested changes conform to the criteria far " actions eligible for categorical exclusion," as specified in 10 CFR 51.22(c)(10). The requested changes will have no impact on the environment. The requested changes do not involve a significant hazards consideration as discussed in the preceding section. The requested changes do not involve a'significant change in the types or significant increase in the amounts of any effluents that may be released offsite, 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 TS and have concluded that they do not involve an unreviewed safety question, or a significant hazards consideration, and will not endanger the health and safety of the public.
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