Letter Sequence Request |
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MONTHYEARML20055C1651983-02-15015 February 1983 Forwards SER Indicating GE 820224 Proposal to Delete Control Rod Drop Accident from Std GE-BWR Reload Package for Banked Position Withdrawal Sequence Plants Acceptable Project stage: Approval ML20211N5261986-12-0909 December 1986 Application for Amend to License NPF-18,consisting of Tech Spec Change Request Re Reload Licensing Package for Cycle 2. Amend Increases Max Critical Power Ratio Fuel Cladding Integrity Safety Limit for Cycle 2.Fee Paid Project stage: Request 1983-02-15
[Table View] |
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Category:OPERATING LICENSES-APPLIATION TO AMEND-RENEW EXISTING
MONTHYEARML20210R3501999-08-13013 August 1999 Application for Amends to Licenses NPF-11 & NPF-18,allowing Performance of CRDM & Ni Replacement to Not Be Considered Core Alterations During Operational Condition 5,Refueling, While Fuel Is in Reactor Vessel ML20210Q3951999-08-0606 August 1999 Application for Amends to Licenses NPF-11 & NPF-18,revising TS Section 3/4.6.4, Vacuum Relief, by Removing Specific Operability Requirements Related to Position Indication for Suppression chamber-drywell Vacuum Breakers ML20209G3551999-07-14014 July 1999 Application for Amends to Licenses NPF-11 & NPF-18 to Revise TS Allowing Both LaSalle County Units to Operate at Uprated Power Level of 3489 Mwt.Proprietary Rev 2 to NEDC-32701P, Power Uprate Sar..., Encl.Proprietary Encl Withheld ML20209D3881999-07-0707 July 1999 Suppl Application for Amends to Licenses NPF-11 & NPF-18, Changing Proposed Degradation Voltage Low Limit Setpoint & Adding High Limit Setpoint & Allowable,Per 981109 Application ML20209D3171999-07-0707 July 1999 Application for Amends to Licenses NPF-11 & NPF-18,revising MCPR Safety Limit & Adding Approved Siemens Power Corp Methodology List of TRs for COLR ML20206T1331999-05-19019 May 1999 Application for Amends to Licenses NPF-11 & NPF-18, Relocating TS Section 3/4.4.4, Chemistry, to UFSAR to Be Consistent with NUREG-1433,rev 1 ML20206J6921999-05-0505 May 1999 Application for Amends to Licenses NPF-11 & NPF-18,to Revise Basis for Evaluation of Vr Exhaust Plenum Masonry Walls for Plant.With One Oversize Drawing ML20195E0471998-11-0909 November 1998 Application for Amends to Licenses NPF-11 & NPF-18,to Modify Degraded Voltage Second Level Undervoltage Relay Setpoint & Allowable Value in TS 3/4.3.3 & TS Table 3.3.3-2 ML20195D9931998-11-0909 November 1998 Application for Amends to Licenses NPF-11 & NPF-18,to Add Automatic Primary Containment Isolation on Ambient & Differential Temperature to High for RWCU Sys Pump,Pump Valve,Holdup Pipe & Filter/Demineralizer Valve Rooms ML20154M4551998-10-16016 October 1998 Application for Amends to Licenses NPF-11 & NPF-18,lowering Power Level Below Which TCV & TSV Closure Scram Signals & EOC-RPT Signal Are Not in Effect.Proprietary Rev 1,suppl 1 to NEDC-31531P,encl.Proprietary Info Withheld ML20217B5721998-04-16016 April 1998 Supplemental Application for Amend to License NPF-11, Changing Leak & Break Detection Isolation Instrumentation. Util Response to RAI & Rev 1 to Calculation L-001443,encl ML20217J2731998-03-24024 March 1998 Application for Amends to Licenses NPF-11 & NPF-18,deleting License Condition 2.C.(30)(a) in Entirety & Revising TS 6.1-3 ML20203G4871997-12-12012 December 1997 Application for Amends to Licenses NPF-11 & NPF-18,modifying Bypass Logic for Msli Valve Isolation Actuation Instrumentation on Condenser Low Vacuum as Stated in Note of TS Tables 3.3.2-1 & 4.3.2.1-1 ML20199K5181997-11-24024 November 1997 Application for Amend to License NPF-11,adding Automatic Primary Containment Isolation on Ambient & Differential Temp High for RWCU Pump,Pump Valve,Holdup Pipe & F/D Valve Rooms. W/Environ Assessment Statement & Calculations ML20211P9171997-10-15015 October 1997 Application for Amends to Licenses NPF-11 & NPF-18, Eliminating Unnecessary Details from Accident Monitoring Instrumentation Surveillance Requirements ML20217C3581997-09-26026 September 1997 Application for Amends to Licenses NPF-11 & NPF-18,adding Ventilation Filter Testing Program ML20141J5521997-08-12012 August 1997 Application for Amends to Licenses NPF-11 & NPF-18,proposing Deletion of Surveillance Requirement 4.7.1.3.c & Addressing Sedimentation Concerns in Intake Structure Under Svc Water Performance Monitoring Program,Iaw GL 89-13 ML20148Q4161997-07-0101 July 1997 Application for Amends to Licenses NPF-11 & NPF-18,revising TSs to Reflect Improvements Made to Control Room Ventilation Air Intake Radiation Monitoring Sys Logic to Reduce Spurious Actuation of Emergency Filtration Mode of Operation ML20148U2551997-07-0101 July 1997 Application for Amends to Licenses NPF-11 & NPF-18,changing Definition of Channel Calibration & Correcting Miscellaneous Errors in TS & Bases ML20141L0311997-05-27027 May 1997 Application for Amends to Licenses NPF-11 & NPF-18, Incorporating Restructured Station Organization,Change to Submittal Frequency of Radiological Effluent Release Rept & Other Administration Changes ML20137W5071997-04-14014 April 1997 Application for Amends to Licenses NPF-11 & NPF-18,changing TS to Reflect Design Change to Trip Logic for Feedwater/Main Turbine Trip Sys Actuation Instrumentation for Reactor Vessel Water Level-High,Level 8 Trip Function ML20134A1781997-01-20020 January 1997 Application for Amends to Licenses NPF-11 & NPF-18, Requesting Relocation of Alarm Only Instrumentation Surveillance Requirements & Adding or Changing Action Statement for Selected TSs ML20135E6551996-12-0202 December 1996 Application for Amends to Licenses NPF-11 & NPF-18,revising Section 3.4.2 SRV Configuration to Include Only 13 of Current 18 SRVs ML20129J4461996-10-31031 October 1996 Application for Amends to Licenses NPF-11 & NPF-18, Eliminating Seismic Monitoring Instrumentation Requirements ML20116A9501996-07-15015 July 1996 Application for Amends to Licenses NPF-11 & NPF-18,revising App A,Ts,Per 10CFR50.90 to Relocate Fire Protection Requirements of Listed TS Sections ML20113C8581996-06-21021 June 1996 Application for Amends to Licenses NPF-11 & NPF-18,including Extension of 18 Month Surveillance Interval & One Time Change to TS to Extend AOT for Each Subsystem of CR & Auxiliary Electric Equipment Room Emergency Filtration Sys ML20107F0541996-04-16016 April 1996 Application for Amends to Licenses NPF-11 & NPF-18, Eliminating Selected Response Time Testing Requirements ML20107A8351996-04-0808 April 1996 Application for Amends to Licenses NPF-11 & NPF-18, Reflecting Transition of Fuel Supplier from GE to Siemens Power Corp.Nonproprietary & Proprietary Versions of EMF-94-217,Rev 1 Repts Encl.Proprietary Rept Withheld ML20097D6451996-02-0909 February 1996 Application for Amends to Licenses NPF-11 & NPF-18,revising TS to Support Elimination of MSIV Leakage Control Sys & Instead Use MSL Drains & Condenser to Process MSIV Leakage ML20096G3261996-01-18018 January 1996 Application for Amends to Licenses NPF-11 & NPF-18,changing Setpoints for Automatic Primary Containment Isolation on MSL Tunnel Differential Temp High & Deleting Automatic Isolation Function on MSL Tunnel Temp High ML20095K6931995-12-21021 December 1995 Application for Amends to Licenses NPF-11 & NPF-18,deleting TS LCO 3.4.2,Action Statement B ML20093D4251995-10-0202 October 1995 Application for Amend to License NPF-11,revising SRV Safety Function Lift Setting Tolerance.Nonproprietary & Proprietary Versions of GE SRV Setpoint Tolerance Relaxation Analysis Encl.Proprietary Analysis Withheld ML20091P8901995-08-28028 August 1995 Application for Amends to Licenses NPF-11 & NPF-18, Eliminating MSIV Leakage Control Sys & Increasing MSIV Leakage Limits,Including Request for Exemption for MSIV Leakages from Acceptance Test Criteria in App J of 10CFR50 ML20084U2921995-06-0808 June 1995 Application for Amends to Licenses NPF-11,NPF-18,NPF-72, NPF-77,NPF-37 & NPF-66.Amends Would Revise SRs & Administrative Requirements Associated W/Edgs ML20084C2221995-05-23023 May 1995 Application for Amends to Licenses NPF-11 & NPF-18, Clarifying Described Equipment out-of-svc Options ML20083P6211995-05-19019 May 1995 Application for Amends to Licenses NPF-11 & NPF-18,revising TS Requirement That Verifies Each Fire Protection Valve in Correct Position at Least Once Per 31 Days ML20082J9261995-04-11011 April 1995 Application for Amends to Licenses NPF-11 & NPF-18,extending Specific 18 Month TS Surveillance Requirements to Allow Surveillance Testing ML20087H7851995-03-31031 March 1995 Application for Amend to License NPF-18,revising SRV Safety Function Lift Setting Tolerances.Nonproprietary & Proprietary GE SRV Setpoint Relaxation Analysis Encl. Proprietary GE SRV Setpoint Relaxation Analysis Withheld ML20078H1441995-01-30030 January 1995 Application for Amend to License NPF-18,requesting Emergency Amend to TS 3.3.1,for One Time Extension of Functional Test for Main Steam Line Isolation Valve - Closure Scram Functional Unit in RPS ML20077S2901995-01-13013 January 1995 Application for Amends to Licenses NPF-11 & NPF-18,to Revise Pressure Alarm Setpoint Allowable Values for ECCS & RCIC Sys Keep Filled Pressure Instrumentation Channels ML20078R7031994-12-14014 December 1994 Application for Amends to Licenses NPF-11 & NPF-18,revising TSs to Minimize Unnecessary Testing & Excessively Restrictive AOT for Certain Actuation Instrumentation. Rev 3 to MDE-83-0485 & Rev 1 to RE-025 Encl.Encls Withheld ML20078B9491994-10-24024 October 1994 Application for Amends to Licenses NPF-11 & NPF-18,revising TS Section 3.6.Exemption Requests from 10CFR50,App J Requirements Encl ML20069J7671994-06-0909 June 1994 Application for Amends to Licenses NPF-11 & NPF-18, Implementing Partial Application of GE ARTS Program.Ge Proprietary Rept NEDC-31531P, ARTS Improvements Program Analysis... Encl.Rept Withheld (Ref 10CFR2.790(b)) ML20065A1871994-03-22022 March 1994 Application for Amends to Licenses NPF-11 & NPF-18,deleting TS 3/4.6.1.5, Primary Containment Structural Integrity ML20063F3081994-01-28028 January 1994 Application for Exigent Amends to Licenses NPF-11 & NPF-18, Revising TS 3.3.1 & 3.3.4 to Extend Surveillance Test Interval from Monthly to Quarterly.Ge Proprietary TS Improvement Analysis Encl.Ge Proprietary Analysis Withheld ML20063E1631994-01-24024 January 1994 Application for Amends to Licenses NPF-11 & NPF-18,deleting Requirement for Response Time Testing Where Required Time Corresponds to Diesel Start Time from TS Table 3.3.2-3,per Line Item 5 of GL 93-05 & NUREG-1366 ML20063B2311994-01-21021 January 1994 Suppl to 931228 Application for Amends to Licenses NPF-11 & NPF-18,changing TS Bases Section B 3/4 2-6 to Include Ref to Plant LOCA Analysis Performed by GE ML20058K3371993-12-10010 December 1993 Application for Exigent Amend to License NPF-11,revising TS 3.4.2, Safety Relief Valves, Adding Footnote to Exempt Safety/Relief Valves 1B21-F013B & 1B21-F013F from Requirements of TS 4.0.3 ML20058A8661993-11-17017 November 1993 Application for Emergency Amends to Licenses NPF-11 & NPF-18,requesting NRC Approval of USQ Re Existing Condition for Which Operator Action Proposed for Tripping Mechanical Vacuum Pump in Place of Automatic Trip ML20058A2591993-11-10010 November 1993 Application for Amends to Licenses NPF-37,NPF-66,NPF-72, NPF-77,DPR-39,DPR-48,NPF-11 & NPF-18 Re Limitations on Radioactive Matl Released in Liquid Effluents,New 10CFR21 & Radioactive Matl Released in Gaseous Effluents 1999-08-06
[Table view] Category:TEXT-LICENSE APPLICATIONS & PERMITS
MONTHYEARML20210R3501999-08-13013 August 1999 Application for Amends to Licenses NPF-11 & NPF-18,allowing Performance of CRDM & Ni Replacement to Not Be Considered Core Alterations During Operational Condition 5,Refueling, While Fuel Is in Reactor Vessel ML20210Q3951999-08-0606 August 1999 Application for Amends to Licenses NPF-11 & NPF-18,revising TS Section 3/4.6.4, Vacuum Relief, by Removing Specific Operability Requirements Related to Position Indication for Suppression chamber-drywell Vacuum Breakers ML20209G3551999-07-14014 July 1999 Application for Amends to Licenses NPF-11 & NPF-18 to Revise TS Allowing Both LaSalle County Units to Operate at Uprated Power Level of 3489 Mwt.Proprietary Rev 2 to NEDC-32701P, Power Uprate Sar..., Encl.Proprietary Encl Withheld ML20209D3171999-07-0707 July 1999 Application for Amends to Licenses NPF-11 & NPF-18,revising MCPR Safety Limit & Adding Approved Siemens Power Corp Methodology List of TRs for COLR ML20209D3881999-07-0707 July 1999 Suppl Application for Amends to Licenses NPF-11 & NPF-18, Changing Proposed Degradation Voltage Low Limit Setpoint & Adding High Limit Setpoint & Allowable,Per 981109 Application ML20206T1331999-05-19019 May 1999 Application for Amends to Licenses NPF-11 & NPF-18, Relocating TS Section 3/4.4.4, Chemistry, to UFSAR to Be Consistent with NUREG-1433,rev 1 ML20206J6921999-05-0505 May 1999 Application for Amends to Licenses NPF-11 & NPF-18,to Revise Basis for Evaluation of Vr Exhaust Plenum Masonry Walls for Plant.With One Oversize Drawing ML20195E0471998-11-0909 November 1998 Application for Amends to Licenses NPF-11 & NPF-18,to Modify Degraded Voltage Second Level Undervoltage Relay Setpoint & Allowable Value in TS 3/4.3.3 & TS Table 3.3.3-2 ML20195D9931998-11-0909 November 1998 Application for Amends to Licenses NPF-11 & NPF-18,to Add Automatic Primary Containment Isolation on Ambient & Differential Temperature to High for RWCU Sys Pump,Pump Valve,Holdup Pipe & Filter/Demineralizer Valve Rooms ML20154M4551998-10-16016 October 1998 Application for Amends to Licenses NPF-11 & NPF-18,lowering Power Level Below Which TCV & TSV Closure Scram Signals & EOC-RPT Signal Are Not in Effect.Proprietary Rev 1,suppl 1 to NEDC-31531P,encl.Proprietary Info Withheld ML20217B5721998-04-16016 April 1998 Supplemental Application for Amend to License NPF-11, Changing Leak & Break Detection Isolation Instrumentation. Util Response to RAI & Rev 1 to Calculation L-001443,encl ML20217J2731998-03-24024 March 1998 Application for Amends to Licenses NPF-11 & NPF-18,deleting License Condition 2.C.(30)(a) in Entirety & Revising TS 6.1-3 ML20203G4871997-12-12012 December 1997 Application for Amends to Licenses NPF-11 & NPF-18,modifying Bypass Logic for Msli Valve Isolation Actuation Instrumentation on Condenser Low Vacuum as Stated in Note of TS Tables 3.3.2-1 & 4.3.2.1-1 ML20199K5181997-11-24024 November 1997 Application for Amend to License NPF-11,adding Automatic Primary Containment Isolation on Ambient & Differential Temp High for RWCU Pump,Pump Valve,Holdup Pipe & F/D Valve Rooms. W/Environ Assessment Statement & Calculations ML20211P9171997-10-15015 October 1997 Application for Amends to Licenses NPF-11 & NPF-18, Eliminating Unnecessary Details from Accident Monitoring Instrumentation Surveillance Requirements ML20217C3581997-09-26026 September 1997 Application for Amends to Licenses NPF-11 & NPF-18,adding Ventilation Filter Testing Program ML20141J5521997-08-12012 August 1997 Application for Amends to Licenses NPF-11 & NPF-18,proposing Deletion of Surveillance Requirement 4.7.1.3.c & Addressing Sedimentation Concerns in Intake Structure Under Svc Water Performance Monitoring Program,Iaw GL 89-13 ML20148U2551997-07-0101 July 1997 Application for Amends to Licenses NPF-11 & NPF-18,changing Definition of Channel Calibration & Correcting Miscellaneous Errors in TS & Bases ML20148Q4161997-07-0101 July 1997 Application for Amends to Licenses NPF-11 & NPF-18,revising TSs to Reflect Improvements Made to Control Room Ventilation Air Intake Radiation Monitoring Sys Logic to Reduce Spurious Actuation of Emergency Filtration Mode of Operation ML20141L0311997-05-27027 May 1997 Application for Amends to Licenses NPF-11 & NPF-18, Incorporating Restructured Station Organization,Change to Submittal Frequency of Radiological Effluent Release Rept & Other Administration Changes ML20137W5071997-04-14014 April 1997 Application for Amends to Licenses NPF-11 & NPF-18,changing TS to Reflect Design Change to Trip Logic for Feedwater/Main Turbine Trip Sys Actuation Instrumentation for Reactor Vessel Water Level-High,Level 8 Trip Function ML20134A1781997-01-20020 January 1997 Application for Amends to Licenses NPF-11 & NPF-18, Requesting Relocation of Alarm Only Instrumentation Surveillance Requirements & Adding or Changing Action Statement for Selected TSs ML20135E6551996-12-0202 December 1996 Application for Amends to Licenses NPF-11 & NPF-18,revising Section 3.4.2 SRV Configuration to Include Only 13 of Current 18 SRVs ML20129J4461996-10-31031 October 1996 Application for Amends to Licenses NPF-11 & NPF-18, Eliminating Seismic Monitoring Instrumentation Requirements ML20116A9501996-07-15015 July 1996 Application for Amends to Licenses NPF-11 & NPF-18,revising App A,Ts,Per 10CFR50.90 to Relocate Fire Protection Requirements of Listed TS Sections ML20113C8581996-06-21021 June 1996 Application for Amends to Licenses NPF-11 & NPF-18,including Extension of 18 Month Surveillance Interval & One Time Change to TS to Extend AOT for Each Subsystem of CR & Auxiliary Electric Equipment Room Emergency Filtration Sys ML20107F0541996-04-16016 April 1996 Application for Amends to Licenses NPF-11 & NPF-18, Eliminating Selected Response Time Testing Requirements ML20107A8351996-04-0808 April 1996 Application for Amends to Licenses NPF-11 & NPF-18, Reflecting Transition of Fuel Supplier from GE to Siemens Power Corp.Nonproprietary & Proprietary Versions of EMF-94-217,Rev 1 Repts Encl.Proprietary Rept Withheld ML20097D6451996-02-0909 February 1996 Application for Amends to Licenses NPF-11 & NPF-18,revising TS to Support Elimination of MSIV Leakage Control Sys & Instead Use MSL Drains & Condenser to Process MSIV Leakage ML20096G3261996-01-18018 January 1996 Application for Amends to Licenses NPF-11 & NPF-18,changing Setpoints for Automatic Primary Containment Isolation on MSL Tunnel Differential Temp High & Deleting Automatic Isolation Function on MSL Tunnel Temp High ML20095K6931995-12-21021 December 1995 Application for Amends to Licenses NPF-11 & NPF-18,deleting TS LCO 3.4.2,Action Statement B ML20093D4251995-10-0202 October 1995 Application for Amend to License NPF-11,revising SRV Safety Function Lift Setting Tolerance.Nonproprietary & Proprietary Versions of GE SRV Setpoint Tolerance Relaxation Analysis Encl.Proprietary Analysis Withheld ML20091P8901995-08-28028 August 1995 Application for Amends to Licenses NPF-11 & NPF-18, Eliminating MSIV Leakage Control Sys & Increasing MSIV Leakage Limits,Including Request for Exemption for MSIV Leakages from Acceptance Test Criteria in App J of 10CFR50 ML20084U2921995-06-0808 June 1995 Application for Amends to Licenses NPF-11,NPF-18,NPF-72, NPF-77,NPF-37 & NPF-66.Amends Would Revise SRs & Administrative Requirements Associated W/Edgs ML20084C2221995-05-23023 May 1995 Application for Amends to Licenses NPF-11 & NPF-18, Clarifying Described Equipment out-of-svc Options ML20083P6211995-05-19019 May 1995 Application for Amends to Licenses NPF-11 & NPF-18,revising TS Requirement That Verifies Each Fire Protection Valve in Correct Position at Least Once Per 31 Days ML20082J9261995-04-11011 April 1995 Application for Amends to Licenses NPF-11 & NPF-18,extending Specific 18 Month TS Surveillance Requirements to Allow Surveillance Testing ML20087H7851995-03-31031 March 1995 Application for Amend to License NPF-18,revising SRV Safety Function Lift Setting Tolerances.Nonproprietary & Proprietary GE SRV Setpoint Relaxation Analysis Encl. Proprietary GE SRV Setpoint Relaxation Analysis Withheld ML20078H1441995-01-30030 January 1995 Application for Amend to License NPF-18,requesting Emergency Amend to TS 3.3.1,for One Time Extension of Functional Test for Main Steam Line Isolation Valve - Closure Scram Functional Unit in RPS ML20077S2901995-01-13013 January 1995 Application for Amends to Licenses NPF-11 & NPF-18,to Revise Pressure Alarm Setpoint Allowable Values for ECCS & RCIC Sys Keep Filled Pressure Instrumentation Channels ML20078R7031994-12-14014 December 1994 Application for Amends to Licenses NPF-11 & NPF-18,revising TSs to Minimize Unnecessary Testing & Excessively Restrictive AOT for Certain Actuation Instrumentation. Rev 3 to MDE-83-0485 & Rev 1 to RE-025 Encl.Encls Withheld ML20078B9491994-10-24024 October 1994 Application for Amends to Licenses NPF-11 & NPF-18,revising TS Section 3.6.Exemption Requests from 10CFR50,App J Requirements Encl ML20069J7671994-06-0909 June 1994 Application for Amends to Licenses NPF-11 & NPF-18, Implementing Partial Application of GE ARTS Program.Ge Proprietary Rept NEDC-31531P, ARTS Improvements Program Analysis... Encl.Rept Withheld (Ref 10CFR2.790(b)) ML20065A1871994-03-22022 March 1994 Application for Amends to Licenses NPF-11 & NPF-18,deleting TS 3/4.6.1.5, Primary Containment Structural Integrity ML20063F3081994-01-28028 January 1994 Application for Exigent Amends to Licenses NPF-11 & NPF-18, Revising TS 3.3.1 & 3.3.4 to Extend Surveillance Test Interval from Monthly to Quarterly.Ge Proprietary TS Improvement Analysis Encl.Ge Proprietary Analysis Withheld ML20063E1631994-01-24024 January 1994 Application for Amends to Licenses NPF-11 & NPF-18,deleting Requirement for Response Time Testing Where Required Time Corresponds to Diesel Start Time from TS Table 3.3.2-3,per Line Item 5 of GL 93-05 & NUREG-1366 ML20063B2311994-01-21021 January 1994 Suppl to 931228 Application for Amends to Licenses NPF-11 & NPF-18,changing TS Bases Section B 3/4 2-6 to Include Ref to Plant LOCA Analysis Performed by GE ML20059E2681993-12-30030 December 1993 Amends 57,57,45,45,93,77,152 & 140 to Licenses NPF-37, NPF-66,NPF-72,NPF-77,NPF-11,NPF-18,DPR-39 & DPR-48, Respectively.Amends Change Instantaneous Limits for Radioactive Liquid & Gaseous Effluent Release Rates ML20058K3371993-12-10010 December 1993 Application for Exigent Amend to License NPF-11,revising TS 3.4.2, Safety Relief Valves, Adding Footnote to Exempt Safety/Relief Valves 1B21-F013B & 1B21-F013F from Requirements of TS 4.0.3 ML20058A8661993-11-17017 November 1993 Application for Emergency Amends to Licenses NPF-11 & NPF-18,requesting NRC Approval of USQ Re Existing Condition for Which Operator Action Proposed for Tripping Mechanical Vacuum Pump in Place of Automatic Trip 1999-08-06
[Table view] |
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Post % Sox 767 (v %. IEr)ois 60600 - 0767 December 9, 1986 Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, DC 20555 LaSalle County Station Unit 2 ~
Subject:
Proposed Amendment to Technical Specification for Facility Operating License NPF Reload Licensing Package for cycle 2 __
NRC Docket Nos. 50-3~14 J. F. Quirk (GE) to O. D. Parr (NRC),
References (a): " General Electric Licensing Topical Report NEDE-24011-P-A, Generic Reload Fuel Application," 9/11/78.
GE Document, NEDE-240ll-P-A, " General (b): Electric Standard Application for Reactor Fue'. , (GESTAR II).
NRC Memorandum, MFN-061-85, C. O. Thomas (c): (NRC) to H. C. Pfefferlen (NRC), " Acceptance for Referencing of Licensing Topical Report NEDE-240ll, Rev. 6, Amendment 8, ' Thermal '"
Hydraulic Stability Amendment to GESTAR II ,
dated April 24, 1985.
NRC Memorandum, L. S. Rubenstein (NRC) i to (d): G. C. Lainas (NRC), " Changes in GB Analys s 983.
of the Control Rod Drop Accident for PlantRelo
Dear Mr. Denton:
roposes to amend Pursuant to 10 CFR 50.90, Commonwealth Edison pility Operating License Appendix A, Technical Specification, tot Fac ff's review and approval and Startup for Cycle 2 These changes are being submitted for lleyour Unit s2.a are in support of the first reload for LaSa This change is essentially the sameith the is currently scheduled for May, 1987.as was approved for Uni to NPF-ll. 00 h
8612180247 861209 DR ADOCK 05000374 PDR RecN w&ectu)fbD 00
~ _
I l i s
December 9, 1986 H. R. Denton Attachment A provides background and discussion. The proposed changes are enclosed in Attachment B. The attached change has received both on-Site and Off-Site review and approval. We have reviewed this amendment request and find that no significant hazards consideration exists. Our review is documented in Attachment C. Attachment D is the GE reload licen-sing submittal. Attachment E is an explanation of the Kg curve for LaSalle Units 1 and 2 which replaces the generic curve included in the present Technical Specifications.
Commonwealth Edison is notifying the State of Illinois of our request for this amendment by transmitting a copy of this letter and its attachments to the designated State Official.
In accordance with the requirements of 10 CFR 50.170, a fee remittance in the amount of $150.00 is enclosed.
Please direct any questions you may have concerning this matter to this office.
Three (3) signed originals and thirty-seven (37) copies of this transmittal and its attachments are provided for your use.
Very tr yours, C. M. Allen Nuclear Licensing Administrator 1m Attachmer us A: Background and Discussion B: Technical Specification Change to NPF-18 C: Evaluation of Significant Hazards Consideration D: GE Document, 23A4735, " Supplemental Reload Licensing Submittal for LaSalle County Station, Unit 2, Reload 1 (Cycle 2)," dated June 1986 E: GE Letter, REP: 84-086, R. E. Parr to L.J.
Bridges dated June 24, 1984 cc: Region III Inspector - LSCS A. Bournia - NRR M. Parker - State of Ill SUBSP IBED AND S ORN to befcire me thik day of .
/ALN/A , 1985 0 . IbQ
' Notary Public' 2482K
. .. . . _ _ _ _ i
s i
ATTACHMENT A TECHNICAL SPECIFICATION CHANGE RBOUEST LASALLE COUNTY STATION UNIT 2 BACKGROUND AND DISCUSSION BACKGROUND i
LaSalle Unit 2, Cycle 2 will utilize 224 BP8CRB299L fuel bundles.
The fuel type is pre pressurized barrier fuel. Information on the Cycle 2 reload may be found in the " Supplemental Reload Licensing Submittal for LaSalle County Station, Unit :2, Reload 1 (Cycle 2)", 23A4735 (AttachmentThese D).
Commonwealth Edison personnel have reviewed this report and commented.
comments and General Electric's response is provided in the enclosure to Attachment D.
Fuel type BP8CRB299L has been approved for inclusion in NEDE-240ll, the General Electric Standard Application for Reactor Fuel (GESTAR II).
This fuel type has been analyzed with approved methods and meets the approved limits of GESTAR. The new fuel type for Unit 2 presents no unreviewed safety questions because the BP8CRB299L bundle design is included in GESTAR.
Shutdown margin during coastdown operation has been analyzed for LaSalle Unit 2 during Cycle 2 (see Reference 4). At a cycle exposure of 7500 mwd /ST (after a coastdown of 725 mwd /ST), shutdown margin has increased Shutdown by 0.12 percent relative to the end-of-rated power exposure point.
margin will continue to increase for greater coastdown exposures.
A The following sections discuss the key features of the reload.
summary of proposed Technical Specification changes is included as an enclosure to this attachment.
- 1. MCPR Safety Limit The MCPR fuel cladding integrity safety limit for Cycle 2 is 1.07.
This is an increase over the 1.06 allowed for the initial core (see Table S.2-3a of the GESTAR). The safety limit is smaller for initial cores because the uncertainties in TIP symmetry and the R Factor are smaller. The associated change to the Technical Specifications is included in Attachment B.
Limiting MCPR Transient I
2.
The Cycle 2 MCPR operating limits required to preclude violation of the fuel cladding integrity safety limit are 1.24 and 8x8R fuel and 1.25 for BP8x8R fuel. These values are based on the Feedwater Controller This i
Failure (FWCF) event analyzed with the ODYN Option B approach.
value is an increase of 0.01 over the initial cycle and so requires a Technical Specification change to Figure 3.2.3-1 (Attachment B).
r 4
s
'The slope change in Figure 3.2.3-1 indicates the chance in limiting transients. For less than 0.736, the limiting transient is the Rod For between 0.736 and 0.754, the Withdrawal Error-(RWE) event.
limiting transient is the Feedwater Controller Failure (FWCF) event.
For greater than 0.754, the limiting transient is the Load Reject Without Bypass (L/R wo BP) event.
Other MCPR related Technical Specification (3/4.2.3) changes were:
The replacement of the present Kg curve with a revised curve, Figure 3.2.3-2 (Attachment B). The revised curve is based on a rated The original core power of 3323 MWth and core flow of 108.5 Mlb/hr.
curve was a-generic curve. Further discussion of this change is provided in Attachment E.
The deletion of the EOC-RPT inoperable provision in the Technical Specification. The analysis was not cost justified for the second cycle but may be included in future cycles.
- 3. Loss of Feedwater Heating The Loss of Feedwater Heating (LoFWH) event was analyzed using the As stated in GESTAR GE BWR simulator Code rather than the REDY Code.
Section S.2.2 (Reference 1), slower core-wideThe transients similarsuch Codeasresults, LoFWH can be analyzed using either of the Codes.
while still conservative, are more realistic than the REDY results.
A feedwater temperature change of 145*F was assumed for the LoFWH event (see Reference 4),. A 145'F change will bound the temperature change of all probable LoFWH events.
- 4. Compliance to ASME Pressure Vessel Code The results of L2C2 analyses for the postulated MSIV closure without direct scram (with flux scram) provided in Reference 5 indicate that the peak steam dome pressure will be 1238 psig and the peak vessel will be 1269 psig. These values are less than the steam dome pressure safety limit of 1325 psig from the Technical Specifications and the ASME vessel overpressurization limit of 1375 psig (110 percent of design pressure). Because the calculated values are less than the limits, the pressure response is acceptable.
- 5. Rod Withdrawal Error The Rod Withdrawal Error (RWE) has been analyzed on a plant / cycle CPR specific basis. The RBM rod block selected setpoint of 107 gives a Adding this CPR to the of 0.18 for both the BP8x8R and the 8x8R fuel. This is equal to the safety limit of 1.07 yields an event LCO of 1.25.
value for the FWCF event, so the RWE and the FWCF are the bounding events.
A corresponding change to Technical specification Table 3.3.6-2 for RBM setpoints for single and dual recirculation loop operation has been proposed in Attachment B.
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- 6. Puel Loading Error Event No Puel Loading Error analysis is required for L2C2. Neither mislocated nor misoriented bundle events are analyzed for BWR-5 reloads.
The mislocated bundle accident is only performed for initial cores. Data from past reloads indicate that the probability of mislocating a fuel bundle so that the CPR violates the safety limit is sufficiently small that plant specific analyses are unnecessary. The NRC has given interim approval for this approach (see GESTAR Section S.2.5.4.1).
The misoriented bundle accident is not analyzed for C-lattice cores such as LaSalle because the misorientation causes an insignificant CPR change. This is due to the uniform water gaps in C-lattice cores vs D-lattice cores. Proper orientation during core loading is also readily verified visually. Por a more detailed discussion, see GESTAR Section S.2.5.4.2.
- 7. Stability Analysis The L2C2 decay ratio at the intersection of the nature circulation line and the 105 percent rod line is 0.60. Since existing Technical Specifications do not allow continued operation in natural circulation, combinations of low flow and high power sufficient to produce high decay ratios are not permitted.
The cycle specific decay ratio of 0.60 is less than the NRC acceptance criteria of 0.80 for plants with no stability Since monitoring the decay ratio is Technical Specifications (see Reference 2).
within the acceptance criteria, the stability of the reload is acceptable. Although the cycle specific analysis is sufficient to demonstrate adequate stability, proposed Technical Specification changes for Single Loop Operation (SLO) stability monitoring have been included as Attachment B to address NRC concerns in this area.
- 8. Single Loop Operation Proposed Technical Specification changes for single loop operation l
have also been provided as Attachment B. Single loop operation was allowed during the first cycle but must be reapproved because it was only approved for the first cycle per Technical Specification Bases 3/4.4.1. These specifications are consistent with those which have been approved for LaSalle Unit 1.
- 9. Loss of Coolant Accident The MAPLHGR limits for the new fuel type BP8CRB299L are included in the GB Licensing Document (Attachment D). The curve for these limits will be added to the LaSalle County Station Unit 2 Technical Specifications. The new Technical Specification curve is included as Attachment B. The existing Technical Specification curve Figure 3.2.1-1 is corrected and included in Attachment B.
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- 10. Rod Drop Accident The Rod Drop Accident (RDA) svent has been statistically analyzed on a generic basis and is no longer analyzed on a plant cycle specific basis. The generic analysis provides assurance that the 280 cal / gram The highest deposition enthalpy deposition limit will not be violated.
of enthalpy calculated was 158 cal / gram. This provides confidence on a 95/95 level that the Technical Specification limit will not be violated in the unlikely event of the postulated Design Basis RDA. The generic RDA analysis has been approved by the NRC (See Reference 3).
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- 11. Conclusion The L2C2 reload as described in the cycle specific licensing document (Attachment D) and supporting documents is acceptable for use in LaSalle Unit 2 Cycle 2. Technical Specification changes described in Attachment B are required. Based on the preceding discussion, on-Site review recommends approval of the reload by Off-Site Review with submission to the NRC for approval prior to the startup.
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.s REFERENCES
- 1. GE Document, NEDE-240ll-P-A, " General Electric Standard Application for Reactor Fuel (GESTAR II)".
- 2. NRC Memorandum, MFN-061-85, C.O. Thomas (NRC) to H. C. Pfefferlen (NRC), " Acceptance for Referencing of Licensing
' Thermal Hydraulic Topical Report Stability Amendment NEDE-240ll, Rev. 6, Amendment 8, to GESTAR II'", dated April 24, 1985.
- 3. NRC Memorandum, L.S. Rubenstein (NRC) to G.C. Lamas (NRC), " Changes in GE Analysis of the control Rod Drop Accident for Plant Reloads (TACS-48058)", dated February 15, 1983.
GE Letter, REF: 86-108, R.E. Parr (GB) to J.L. Anderson, " General 4.
Electric's Responses to Edison's Comments on LaSalle County 27, 1986, Unit 2 Cycle 2 Draft Reload Licensing Submittal", dated June Attachment D, Enclosure.
- 5. GE Document, Additional Information Regarding the Supplemental Reload Licensing Submittal for LaSalle 2 Reload 1/ Cycle 2 (Attachment D, Enclosure).
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IDICLOSURE TO ATTACHMENT A SUM (ARY OF PROPOSED CHANGES The following Technical Specification changes will support operation of LaSalle County Station Unit 2 during Cycle 2.
Technical Specification 2.1, Safety Limits The MCPR fuel cladding integrity safety limit is changed from 1.06 to 1.07 for two recirculation loop operation, and from 1.07 to 1.08 for single recirculation loop operation. I Safety Limits Bases Based Tables B2.1.2-1, B2.1.2-2, B2.1.2-3, and B2.1.2-4 are changed to reflect the reload core inputs to the statistical model which determines the MCPR safety limit. The reload values were obtained from GESTAR (Tables S.2-1, S.2-2, S.2-2c and Figure S.2-la).
The rated thermal power and flow of the GESTAB model is not the same as for LaSalle Units 1 and 2 (the model uses a power of 3293 MWth and core flow of 102.5 M1b/hr). The results of the analysis are considered to be bounding for plants rated at 3323 MWth and 108.5 Mlb/hr core power and flow, respectively. This analysis determines the value of the safety limit itself (1.07 for dual loop reload cores). The actual licensed plant specific rated power and flow values were used in the evaluation of transients to determine the cycle specific MCPR operating limit.
Technical Specification 3/4.2.1, Average Planar Linear Heat Generation Rate Reference to Figure 3.2.1-2, which contains the MAPLHGR vs Exposure curve for the reload fuel type BP8CRB299L, was added to the specification.
Fiqures 3.2.1-1 and 3.2.1-2, MAPLHGR limit vs Exposure Curves Figure 3.2.1-1 was changed to indicate the correct initial cycle fuel type designations.
Figure 3.2.1-2 was added to provide the MAPLHGR limit vs Exposure curve for the reload fuel type BP8CRB299L. A separate graph was used for the reload fuel in order to avoid confusion with the initial fuel curves.
Technical Specification 3/4.2.3, Minimum Critical Power Ratio The initial cycle provision for operation with the EOC-RPT system inoperable has been deleted. The analysis necessary to support ti l, provision was not justified for in the second cycle but may be included in future cycles.
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Fiqure 3.2.3-1, MCPR vs at Rate Flow The present curve has been replaced by a curve which reflects the results of the cycle specific transient analysis for Cycle 2. For less than 0.736 the limiting transient is the Rod Withdrawal Error (RWE) event.
For between 0,736 and 0.754, the lLaiting transient is the Feedwater Controller Failure (PWCF). For greater than 0.754, the limiting transient is the Load Reject Without Bypass (L/R wo BP) event.
Fiqure 3.2.3-2, Kg curve The present curve has'been replaced by a revised curve which is based on a rated core power of 3323 MWth and core flow of 1.08.5 M1b/hr.
The original curve was a generic curve.
Technical Specification 3.3.4.2 BOC-RPT INSTRUMENTATION ACTION Statements d and e were revised to remove the reference to Specification 3.2.3, since no RPT-inoperable analysis was performed for the reload. Power reduction requirements (to below the operability range of the RPT system at 30% power) were inserted in the event that restoration of an inoperable trip system (s) cannot be accomplished within the specified time period.
Technical Specification 3/4.4.1 Recirculation System The Recirculation Gyatem Specification is revised to raflect the MCPR Safety Limit for Single Loop Operation (SLO) of 1.08. Additionally, the actions required for Thermal-Hydraulic Stability monitoring in SLO are revised to increase assurance of avoiding possible unstable conditions. The specification is changed to match the previously approved recirculation specification for LaSalle Unit 1 Technical Specifications.
Figure 3.4.1.1-1 is added to support stability monitoring in Specification 3/4.4.1.
Bases for Specification 3/4.4.1 The Bases for Specification 3/4.4.1 is revised to reflect that reload cycles are analyzed for SLO. A paragraph is added to reflect the basis for the stability monitoring required during SLO.
Table 3.3.6-2 CONTROL ROD WITHDRAWAL BLOCK INSTRUMENTATION SETPOINTS Table 3.3.6-2 is revised to incorporate the required RBM setpoint change (RBM Setpoint of 107%).
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