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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] |
Text
- Y . Commonwealth Edloon M m ,, One First N-$onal Plan. Chicago, Illinois
\ . Address Heply to: Post Offee Box 767
\ Chicago,Illinoit 60690 0767 June 16, 1987 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555
Subject:
LaSalle County Station Units'1 and 2 proposed Amendments to Technical Specifications for Facility Operating License NpF-11 NRC Docket No. 50-373 References (a): Federal Register Vol. 51 No. 44 dated Thursday, March 6, 1986.
Dear. Sir:
pursuant to 10CFR 50.90 Commowealth Edison proposes to amend Facility Operating License NpF-11. This one time only amendment is being submitted for your staff's review and approval and is in accordance with reference (e).
The amendment requested will allow performance of the snubber surveillance for LaSalle Unit 1, second fuel cycle to correspond to the scheduled second refuelling. This change is required due to the extended interval between completion of snubber testing and unit 1 startup.
Attachment A provides an introduction and discussion. Attachment B provides a discussion of the major causes of snubber failure during LaSalle Unit.1.first refueling. Attachment C provides copies of the changes to be made to the Facility License. Commonwealth Edison has reviewed this document and finds that no significant hazards exists. This review is
. documented in Attachment D.
We request approval for this change as soon as possible. The change is required prior to October. If for any reason the change would not be approved prior to that date Commonwealth Edison would need to know as early as possible to schedule a unit outage and obtain vendor support necessary to perform snubber surveillances. The effective date of this amendment when approved should be the date of issuance.
(
\
h(# il 04 49 hon 8706230405 870616 g
PDR ADOCK 05000373 p PDR
Commonwealth Edison is notifying the State of Illinois of our l request for this amendment by transmitting a copy of this letter and attachments to the designated state official.
In accordance with 10 CFR 170, a fee remittance in the amount of I
$150.00 is also enclosed.
If you have any additional questions regarding this matter, please contact this office.
I V tr y yours, C. M. Aller' Nuclear Licensing kdministrator Attachments cc; Paul Shemanski - NRR Regional Administrator - RIII NRC Resident Inspector - LSCS M. C. Parker - IDNS l
l 3212K
4 ATTACHMENT A TECHNICAL SPECIFICATION CHANGE REQUEST- ;
LASALLE COUNTY STATION UNIT.1 l
INTRODUCTION-Commonwealth Edison performed the initial' snubber functional test surveillance for Technical Specification 3/4.7.9 at' LaSalle County Nuclear Station Unit 1 (LSCS-1), during the, Unit 1 first refueling outage. The surveillance was of extended length, lasting from December 1985 until May 1986. Power operation. )
sof LSCS-1 following its first refueling did not' commence until September 1986.- The surveillance schedule requirements of Technical Specification .
3/4.7.9, when coupled with the~ extended length of the snubber surveillance and' .l first' refueling outage, dictate that the next snubber surveillance for LSCS-1 !
be done during the course of.the second fuel cycle. j i
' Based on the following discussion, commonwealth Edison'(LcSalle County Nuclear {
Station) is proposing to make a one time amendment to Unit 1 Technical l Specification 3/4.7.9 (operating license NPF-ll). The amendment would allow !
the second LSCS-1 snubber functional test surveillance to be scheduled 18 q months from the September 1986 startup date. This amendment would bring the snubber functional test surveillance back into synchronization with the refueling schedule, and allow the second required surveillance.to be done at .
the.second refueling c.itage, rather than during the course of the second fuel 4 cyclo.
DISCUSSION The LSCS-1 safety related snubbers were initially functionally tested during the Unit 1 first refueling outage. This surveillance covered all of the j unit's 1235 safety related snubbers, and 104 snubbers failed to meet test acceptance limits for operability under Technical Specification 3/4.7.9. The
's snubber. population is made up exclusively of mechanical type units, manufactured by pacific Scientific Company (pSA). The following dates are associated with the initial LSCS-1 snubber surveillance:
LSCS-1 shutdown for first refueling-- October 18, 1985, :
First snubber tested for surveillance - December 5, 1985, Snubber surveillance completed - May 20, 1986, l LSCS-1 restart following first refueling outage - September 18, 1986. J l
j 4
Technical Specification 3/4.7.9 requires that all snubbers required to l maintain the structural integrity of reactor coolant system and other safety !
related piping be functionally tested at first refuel, and every 18 months j thereafter during shutdown. In addition, the bases of the Technical )
Specification assumes that the frequency of snubber failures is constant over l time. These two factors dictate that the next LSCS-1 snubber test j surveillance be performed within 18 months of the date the first snubber was l tested at first refuel, in order for the bases of the Technical Specification to be met for the snubber population at all times. The extended length of the first refuel surveillance, coupled with the four month time period between surveillance completion and unit restart, resulted in having a significant portion of the 18 month interval (for the second rnubber surveillance) expire, while the unit was still in cold shutdown for its first refueling outage. The following dates are associated with the upcoming second snubber surveillance for LSCS-1:
First snubber tested - initial surveillance - December 5, 1985, 18 months after first snubber tested - June 5, 1987, 22.5 months after first snubber tested - October 19, 1987, LSCS-1 second refueling outage shutdown date - March 15, 1988.
The LSCS-1 snubber functional test surveillance is no longer in synchronization with the unit refueling schedule, even when the 25% extension (4.5 months) allowed by Technical Specifications is applied. Technical Specification 3/4.7.9 presently requires that all 104 test failures from the first surveillance be tested during this second surveillance, as well as an additional random sample. LSCS-1 is in a position where the second snubber functional test surveillance will be required to be done during the course of the second fuel cycle. Although a short mid-cycle outage began in June of 1987 for Unit 1, it is of insufficient length to cover the anticipated functional test duration. Therefore, if the snubber surveillance is performed during the second cycle, it will require extending the present outage or create another outage, which is highly undesirable.
Commonwealth Edison proposes to amend Technical Specification 3/4.7.9 on a one time basis for the second LSCS-1 snubber functional test surveillance. This amendment would schedule the second snubber functional test surveillance 18 months from the commencement of power operation for Cycle 2. The revised due dates for the affected surveillance are as follows:
LSCS-1 restart following first refueling outage - September 18, 1986, 18 months following restart - March 18, 1988, 22.5 months following restart - August 1, 1988.
This proposed amendment has been discussed in general terms in conversations (on March 24, 1987 and April 6, 1987) between Commonwealth Edison personnel and members of the Nuclear Reactor Regulation (NRR) staff.
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TECHNICAL JUST1FICATIONE j The_ technical justification for the' proposed technical specification amendment is based on the following:
- the safety related snubber population of LSCS-1 was fully operable-at the start of the second fuel cycle,
- there is a greatly reduced failure potential for snubbers when the unit is in cold shutdown conditions,
- in a majority of cases, the mechanical snubber will still be able to perform its primary function (limit piping motion and stress during dynamic events) while in a degraded / failed condition,
- all safety related mechanical snubbers in LSCS-1 are to be visually I inspected during the second fuel cycle, and
- a snubber reduction program is being implemented at LSCS-1.
- 1. All safety related snubbers were tested during the surveillance performed at the LSCS-1 first refueling outage, with 104 snubbers failing to meet j acceptance limits. Details of this surveillance can be obtained in Licensee Event Report (LER) 373/86-036. . Completion of the surveillance, along with the associated corrective actions for the test failures, returned the unit's snubber population to a baseline one hundred percent operable condition. This is the same condition the population was in at the beginning of first cycle operation.
i Technical Specification 3/4.7.9 only requires the initial snubber !
functional test surveillance to be done at the unit's first refueling outage, regardless of the length of the first cycle. The proposed amendment would extend the maximum time interval between the first and second snubber surveillance from approximately 22 months (18 months plus-25% extension / to 26 months, a time frame which is still less than the length of the first cycle for LSCS-1. Since the entire snubber population on LSCS-1 was restored (during the initial surveillance) to an operable condition equivalent to what it was at the start of the first fuel cycle, the requested amendment would be consistent with what Technical Specification 3/4.7.9 allows for a plant with a fully tested and operable snubber population for a first fuel cycle.
- 2. The bases for Technical Specification 3/4.7.9 assumes that the frequency of snubber failures, and the initiating events which require them to protect plant piping, are constant over time. While these assumptions are useful in establishing surveillance schedules which assure a high level of snubber protection for piping, they do not reflect the actual conditions of snubber service.
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The occurrence of initiating events are not constant over time, since it is not possible for many of the events to occur while the unit is in cold shutdown. _ Examples of such initiating events for piping response, given in Section 3.9 of the Updated Final Safety Analysis Report (UFSAR),
include: loss of coolant accidents, main steam safety relief valve operation, turbine trips, and rupture of high energy piping. It is very conservative to assume that snubbers which are designed to help plant piping accommodate loads from these events, or in combination with the seismic events as postulated in Section 3.9 of the UFSAR, can potentially see such loads while the unit is in cold shutdown.
The frequency of snubber. failures is also not constant over time, since the factors which cause most of the LSCS-1 mechanical snubber failures are absent, or greatly reduced while the unit is in cold shutdown. Attachment B details the four prevailing causes of snubber failures for LSCS-1 during its first refueling outage, and the potential for inducing snubber failures from the same mechanisms during cold shutdown conditions. The prevailing causes of snubber failures were:
-low frequency steady state vibration of system piping,
-transient forces due to system startup/ shutdown,
-overheating of snubber which causes lubricant breakdown, and
-corrosion of snubber internals.
Since a significant portion of the snubber surveillance interval (between the first and second surveillance) was spent with the unit in cold shutdown, which is a period of reduced failure potential for the snubber population, the proposed amendment to extend the surveillance interval should not have un adverse impact on snubber operability or their ability to maintain the structural integrity of critical piping systems.
- 3. The mechanical snubbers which make up the LSCS-1 population, manufactured exclusively by Pacific Scientific Company (pSA), fulfill their required role of maintaining the structural integrity of critical piping systems by performing two functions. The primary function of each snubber is to activate and become rigid, at or below a specified acceleration level, to limit piping motion and stresses during the dynamic events postulated in the UFSAR. Each snubber also fills a secondary role of moving freely in the absence of dynamic loads, to allow normal system thermal expansion to occur without restrictions, and the accompanying bending stresses.
4 The majority of the snubbers that failed to meet test criterion during the LSCS-1 first refueling outage did not meet drag force limits, which is a measure of their ability to perform their secondary function. Test results from LSCS-1 show that mechanical snubbers tend to become more difficult to stroke as they fail in service, due to degradation of their close tolerance internal parts, and eventually they become rigid assemblies. Snubbers which exceeded drag force criterion still met activation acceleration limits in tension and compression, and would have done so even if locked rigid. Therefore, the snubbers which failed test limits for their secondary role could have fulfilled their primary function of protecting plant piping systems during design bases dynamic events, should they have occurred during the first fuel cycle.
The tendency of pSA mechanical snubbers to fail in a rigid mode, rather than to become free moving is supported by snubber tests which have been previously completed at LaSalle Station (1235 tests on Unit I and 1027 tests on Unit 2) and at other commercial nuclear power facilities.
Analysis of the effects the failed snubbers had on plant piping in LSCS-1 included fatigue and usage calculations, which evaluated the stresses induced when snubbers exceeded drag force limits or went rigid during piping system thermal cycles. None of the failures were found to have safety significance alone or in combination, and all associated piping j systems were still able to meet the ASME Code thermal stress and fatigue '
limits specified in Chapter 3.0 of the UFSAR.
Extending the time interval between the first and second snubber surveillance does not appear to pose a significant increase in the risk of losing the structural integrity of safety related piping systems. The tendency of pSA snubbers to fail in a rigid manner when degraded in service, means that failed snubbers will still be likely to restrain pipe motions during dynamic events. The additional pipe thermal stresses and fatique considerations associated with snubbers which fail to stroke freely generally require multiple system thermal cycles over an extended period of years to approach piping system design limits. The proposed amendment will delay the next LSCS-1 snubber surveillance for a few months during reactor power operation, so their should be minimal fatigue / usage impact of plant piping systems, even if some snubbers exceed drag force limits during the period prior to the test.
- 4. All safety related mechanical snubbers in LSCS-1 are due to be visually inspected per surveillance requirement 4.7.9.b during the second fuel cycle. The snubbers in the primary containment, which are normally inaccessible during reactor power operation, will be inspected during a short unit outage in June 1987. The remaining snubbers are scheduled to be inspected in the fall of 1987. Visual inspection of the snubber j population gives assurance that all snubbers are in good overall condition >
and operable, and gives confidence tnat widespread failures of snubbers due to events such as unanticipated system water hammer has not occurred.
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- 5. Commonwealth Edison is presently implementing a snubber reduction program at LSCS-1 and 2, to remove snubbers via system reanalysis, which employs revised design criteria. The current schedule has snubber reduction being completed prior to the end of the second refueling outage for each unit. ,
Modifications are now being prepared to reduce the LSCS-1 anubber l population to approximately 300 units. Snubbers which failed testing at first refuel, and those in known areas with the greatest potential for failure, are being given priority for removal under the program.
The proposed amendment would allow the station to implement the snubber i '
reduction program prior to performing the next snubber surveillance, thereby reducing the number cf possible test specimens. The reduced snubber population will limit the length of future snubber surveillances, even if all snubbers in the population must be tested during a given surveillance. This should insure that the snubber surveillance remains in synchronization with plant refueling outages in the future, without further Technical Specification amendments.
CONCLUSION Based on the previous discussion, commonwealth Edison (LaSalle County Nuclear Station) proposes to make a one time amendment to Unit 1 Technical Specification 3/4.7.9, as indicated in Attachment C. The amendment would allow the second LSCS-1 snubber functional test surveillance (surveillance requirement 4.7.9.e) to be conducted 18 months from the commencement of power operation for Cycle 2. Since the bases for Technical Specification 3/4.7.9 can be expected to be maintained with this amendment, Commonwealth Edison requests NRC review and approval of the proposed Unit 1 operating license amendment.
1 ATTACHMENT B MAJOR CAUSES OF SMUBBER FAILURES DURING INITIAL LSCS-1 SURVEILLANCE l
cause-Low frequency steady state vibration of system piping.
Description - prolonged exposure of the snubber to vibration leads to erosion and wear of close tolerance internals over time. The forces generated are due to turbulent flow in piping during i system full flow operation. Most LSCS-1 systems were in layup or under maintenance activity during the first refuel outage. Snubbers exposed only briefly to vibration during j system flow tests.
Cause - Transient forces due to system startup/ shutdown.
Description - Normal low level transient loads in systems associated with )
pump starts / stops, valve opening / closure, or trapped air.
The forces are usually below snubber capacity rating, and have negligible impact on system piping. These forces do not occur in cold shutdown for the same reasons as the low frequency steady state vibration case. Repeated application of these loads over time caused wear and cracking of snubber internals at LSCS-1.
Cause- Overheating of snubber which causes lubrication breakdown.
Description- Exposure of mechanical snubbers to temperatures above 250*F leads to breakdown of the snubber lubricant, causing unit to fail drag tests, or go completely rigid. This can occur if the snubber is installed in an area where high ambient temperatures exists, or if it is near a large piece of equipment, such as a valve bonnet, and sees high radiant heat loads. This failure mechanism is absent in cold shutdown with the unit depressurized and all systems at temperatures less than 200*F. :
Cause - Corrosion of snubber internals.
Description - Mechanical snubbers installed in areas where they were soaked or '
sprayed with water had internals corrode, causing failure.
Water sources include valve bonnet and packing leaks, pipe flange leaks and pump seal leaks. In many cases, plant systems ;
are depressurized and drained for maintenance while the unit is {
in cold shutdown, and leakage sources are eliminated.
Additional information on Unit 1 snubber surveillance may be obtained from Licensee Event Report 373/86-036. ,
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