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Category:OPERATING LICENSES-APPLIATION TO AMEND-RENEW EXISTING
MONTHYEARML17300B3301999-09-14014 September 1999 Application for Amends to Licenses NPF-41,NPF-51 & NPF-74, Making Listed Administrative Changes to TS 5.5.2 & TS 5.6.2 Re Primary Coolant Sources Outside Containment & Annual Radiological Environmental Operating Rept ML17313A9541999-05-26026 May 1999 Application for Amends to Licenses NPF-41,NPF-51 & NPF-74, Reducing Spurious Reactor Trip Hazards Associated with Setpoints While Maintaining Plant Protection ML17313A8331999-02-26026 February 1999 Re-issue of Application for Amend to Licenses NPF-41,NPF-51 & NPF-74,re TS 3.5.3,ECCS - Operating,To Extend Completion Time for One Inoperable LPSI Subsystem from 72 Hours to 7 Days ML17313A8301999-02-26026 February 1999 Application for Amends to Licenses NPF-41,NPF-51 & NPF-74, Revising TS 3.5.3, ECCS - Operating, by Extending Completion Time for One Inoperable LPSI Subsystem from 72 Hours to 7 Days ML17313A7091998-12-16016 December 1998 Application for Amends to Licenses NPF-41,NPF-51 & NPF-74, Changing Condition G of TS 3.8.1 to Ensure That Appropriate Actions Will Be Taken to Prevent Double Sequencing of safety-related Loads ML17313A1571997-12-17017 December 1997 Application for Amends to Licenses NPF-41,NPF-51 & NPF-74, Respectively.Amends Change TS 3/4.8.2 & Associated Bases 3/4.8,allowing Replacement of Existing Class 1E,125 Volt Dc Batteries W/Low Specific Gravity Cell Batteries ML17312B6391997-08-28028 August 1997 Application for Amend to License NPF-51,allowing one-time Extension of Required Surveillance Interval for Msi Sys Portion Only of ESFAS Logic ML17312B4651997-05-23023 May 1997 Rev to 950418 Application for Amends to Licenses NPF-41, NPF-51 & NPF-74,revising TS Section 3/4.4.4, Steam Generators & Associated Bases to Allow Installation of Tube Sleeves as Alternative to Plugging Defective SG Tubes ML17312B1541996-12-27027 December 1996 Application for Amends to Licenses NPF-41,NPF-51 & NPF-74 to Revise TS LCO 3.6.1.3.b of TS 3/4.6.1.3, Containment Air Locks, Bases 3/4.6.1.4, Internal Pressure & 3/4.6.1.6, Containment Structural Integrity. ML17312A8431996-06-28028 June 1996 Application for Amends to Licenses NPF-41,NPF-51 & NPF-74, Amending TS 3/4.5.2, ECCS Subsystems-Operating & Bases to Change SRs 4.5.2.d.2 & 4.5.2.d.3 to Reflect Design Basis Requirements for Anhydrous Trisodium Phosphate ML17300B2631996-06-17017 June 1996 Application for Amends to Licenses NPF-41,NPF-51 & NFP-74, Respectively,Changing Sections 1.10 & 3.2.8 & Associated Bases for Obtaining Thyroid Dcf Used in Definition of Dose Equivalent I-131 ML17312A6471996-04-0101 April 1996 Application for Amend to License NPF-51,revising TS 3/4/9.6 to Temporarily Allow Use of Hoist Instead of Refueling Machine for Movement of Fuel Assembly at Core Location A-07 ML17312A6381996-03-26026 March 1996 Application for Amend to License NPF-51,revising TS 3/4.9.6 to Increase Refueling Machine Overload Cut Off Limit to 2,000 Lb in Effort to Free Stuck Fuel Assembly from Core Location A-06 ML17312A6301996-03-26026 March 1996 Application for Amend to License NPF-51,revising TS 3/4.9.6 to Relocate Refueling Machine Overload Cut Off Limit from TS 3/4.9.6 to Plant UFSAR Per Criteria in 10CFR50.36 & Rev 1 of NUREG-1432, STS for Combustion Engineering Plants. ML17312A6331996-03-23023 March 1996 Application for Amend to License NPF-51,revising TS SR 4.8.2.1.e, DC Sources, to Suspend Provision of TS 4.0.1 & 4.0.4 for Battery Capacity Testing Requirements Until Entry Into Mode 4 Following Sixth Refueling Outage ML17312A6251996-03-22022 March 1996 Application for Amends to Licenses NPF-41,NPF-51 & NPF-74, Modifying TS 3/4.8.1 for Purposes of Implementing Recommended Changes from NUREG-1432,GL 94-01 & GL 96-05 ML17312A5411996-02-0909 February 1996 Suppl Application for Amends to Licenses NPF-41,NPF-51 & NPF-74,implementing New Option B to 10CFR50,App J, Primary Reactor Containment Leakage Testing for Water-Cooled Power Reactors. ML17312A5221996-02-0101 February 1996 Application for Amends to Licenses NPF-41,NPF-51 & NPF-74, Respectively,Changing TS Sections 2.2.1 (Table 2.2-1) & 3/4.3.2 (Tables 3.3-3 & 4.3-2) to Specify Addl Restriction for Allowed Low Pressurizer Pressure Trip Setpoint ML17311B3131995-12-19019 December 1995 Application for Amends to Licenses NPF-41,NPF-51 & NPF-74, Revising TS for Implementation of 10CFR50,App J,Option B for Determining Test Frequency for Containment Leakage Rate Testing ML17311B2651995-11-0707 November 1995 Application for Amend to Licenses NPF-41,NPF-51 & NPF-74, Adopting Approved STS Format & Content of Section 5.0, Design Features, as Modified by Approved Changes to Improved STS ML17311B0931995-08-0303 August 1995 Application for Amends to Licenses NPF-41,NPF-51 & NPF-74, Adding Listed Analytical Method & Associated NRC SER to TS 6.9.1.10, Colr. Prorpietary PVNGS-3 Cycle 6 ECCS Performance Analysis Encl.Proprietary Analysis Withheld ML17311A9501995-06-13013 June 1995 Application for Amends to Licenses NPF-41,NPF-51 & NPF-74, Revising TS Sections 3.5.1,3.5.2,3.7.11,3/4.8.1.1 & Bases to Extend AOTs for Sit,Lpsi Subtrain & EDG & Adding Bases for Extended Aots,Consistent w/NUREG-1366 & GL 93-05 ML17311A8631995-05-0202 May 1995 Application for Amends to Licenses NPF-41,NPF-51 & NPF-74, Revising TS 3.1.2.6,Figure 3.1-1, Min Borated Water Vols by Relocating Plant Elevations That Correspond to Min Required Water Vols for Spent Fuel Pool to Site Procedures ML17311A7531995-03-31031 March 1995 Application for Amends to Licenses NPF-41,NPF-51 & NPF-74. Amends Would Clarify Shutdown Margin Definition,Change shut- Down Margin Applicability & SRs to Comply W/Safety Analysis Assumptions for Subcritical Inadvertent CEA Withdrawal ML17311A5611994-12-28028 December 1994 Application for Amends to Licenses NPF-41,NPF-51 & NPF-74, Revising TS Sections 3.9.6 & 4.9.6.1 Re Refueling Machine Overload Cut Off Limit ML17311A4901994-12-0707 December 1994 Application for Amends to Licenses NPF-41,NPF-51 & NPF-74, Requesting TS 3/4.7.5 to Change Bases for Ultimate Heat Sink from Providing 27 Day Cooling Water Supply to Providing 26 Day Cooling Water Supply ML17311A4481994-11-30030 November 1994 Application for Amends to Licenses NPF-41,NPF-51 & NPF-74, Revising LCO 3.2.1 & 3.2.4 & Associated Bases ML17311A4241994-11-22022 November 1994 Application for Amend to License NPF-41,proposing TS Section 3/4.7.1 by Adding Note to Table 3.7.2 ML17310B4491994-07-12012 July 1994 Application for Amends to Licenses NPF-41,NPF-51 & NPF-74, Requesting Amend to TS Table 3.3-3, ESF Actuation Sys Instrumentation. ML17310B4341994-06-17017 June 1994 Application for Amends to Licenses NPF-41,NPF-51 & NPF-74, Increasing Min Nitrogen Accumulator Pressure ML17310B4071994-06-17017 June 1994 Application for Amend to License NPF-41,NPF-51 & NPF-74 Proposing Ts,By Removing Five Tables of Component Lists, Per GL 91-08 ML17310B2691994-05-0404 May 1994 Application for Amends to Licenses NPF-41,NPF-51 & NPF-74, Clarifying TS LCO 3.4.8.3 & Surveillance Requirement 4.4.2.3.1 Applicability During Steady State Conditions in RCS Heatup/Cooldown Evolutions ML17310B1641994-03-28028 March 1994 Application for Amends to Licenses NPF-41,NPF-51 & NPF-74, Changing Min Condensate Storage Tank Indicated Level from 25 Ft to 29.5 Ft ML17310B0591994-02-18018 February 1994 Application for Amends to Licenses NPF-41,NPF-51 & NPF-74, Revising TS Figure 3.2-1 for Units 1 & 3 & TS 3/4.1.1.4 & Bases 3/4.1.1.4 for Units 1,2 & 3 to Allow Units 1 & 3 to Operate at 100% Full Power Under Reduced Temp Regimen ML17310A8861994-01-0404 January 1994 Application for Amends to Licenses NPF-41,NPF-51 & NPF-74 Modifying Ts,Implementing Recommended Changes from GL 93-05, Line -Item TS Improvements to Reduce SR for Testing During Power Operation. ML17310A8891994-01-0404 January 1994 Application for Amends to Licenses NPF-41,NPF-51 & NPF-74, Proposing Changes to TS Section 3/4.2.3, Azimuthal Power Tilt, & Bases,Requesting Toprovide More Restrictive Azimuthal Power Tilt Limit When COLSS Out of Svc ML17310A8821993-12-30030 December 1993 Application for Amends to Licenses NPF-41,NPF-51 & NPF-74, Changing TS Section 3/4.3.2 by Modifying Tables 3.3-4,3.3-5 & Adding Figure 3.3-1 ML17310A8491993-12-0202 December 1993 Application for Amends to Licenses NPF-41,NPF-51 & NPF-74 Modifying TS by Removing Schedular Requirements for Type a Test to Be Performed Specifically at 40 + or - 10 Month Intervals ML17310A7871993-11-0505 November 1993 Application for Amend to License NPF-51,revising LCOs 3.5.2, ECCS, 3.6.2-1, CSS, 3.7.1.2, Afs, 3.7.3, EWS, 3.7.6, Ecw Sys & 3.7.11, Sdcs Under Exigent Circumstances ML17310A7251993-10-27027 October 1993 Application for Amends to Licenses NPF-41,NPF-51 & NPF-74, Revising TS Section 1.18,6.9.1.8,6.14.c & 6.15.1 in Order to Implement Revised 10CFR50.36a Regulation That Now Allows Radioactive Effluent Release Rept to Be Submitted Annually ML17310A6131993-09-0808 September 1993 Application for Amend to License NPF-41,requesting TS Section 6.9.1.10 to Add Analytical Method Suppl Entitled Sys 80 Inlet Flow Distribution to List of Methods Used to Determine Core Operating Limits ML17310A5181993-08-0505 August 1993 Application for Amends to Licenses NPF-41,NPF-51 & NPF-65, Requesting Change to Word Pressurizer to RCS for Item 4 in Tables 3.3-10 & 4.3-7 ML17310A4181993-06-30030 June 1993 Application for Amends to Licenses NPF-41,NPF-51 & NPF-74, Revising TS 3/4.3.2 to Request Addl Operating Margin in Time Response of Turbine Driven AF Pump to SG Low Level Signal ML17306B1981992-12-28028 December 1992 Application for Amends to Licenses NPF-41,NPF-51 & NPF-74, Respectively,Revising TS 3/4.3.1,Table 4.3-1 & 3/4.3.2,Table 4.3-2,to Change Surveillance Requirements from Monthly to Quarterly for Several Channel Functional Tests ML17306A6891992-04-27027 April 1992 Application for Amends to Licenses NPF-41,NPF-51 & NPF-74, Amending Tech Spec 3/5.7.6 & Bases of Section 3/4.7.6 to Reduce Essential Chilled Water Sys out-of-svc Time from 7 Days to 72 H ML17306A6091992-03-20020 March 1992 Application for Amends to Licenses NPF-41,NPF-51 & NPF-74, Revising TS Section 3/4.9.9 to Change Containment Purge Valve Isolation Sys Operability Requirements for Consistency W/Other Containment Penetration Operability Requirements ML17306A3761991-12-30030 December 1991 Application for Amends to Licenses NPF-41,NPF-51 & NPF-74, Revising TS Section 3.6.1.7 Action Statements Re Containment Purge Supply & Exhaust Valves for Consistency W/Other Containment Sys Action Requirements ML17306A3541991-12-20020 December 1991 Application for Amend to License NPF-74,adding Sentence to TS Section 5.3.1 to Allow Substitution of Up to Total of 80 Fuel Rods Clad W/Advanced zirconium-based Alloys Other than Zircaloy-4 in Two Fuel Assemblies.Rept Withheld ML17305B7301991-09-0909 September 1991 Application for Amends to Licenses NPF-41,NPF-51 & NPF-74, Changing Tech Spec 3/4.7.11, Shutdown Cooling Sys to Delete auto-closure Interlock Surveillance of Surveillance Requirement 4.7.11b,per Generic Ltr 88-17 ML17305B7161991-08-28028 August 1991 Application for Amends to Licenses NPF-41,NPF-51 & NPF-74. Proposed Amends Resolve Inconsistent Application of Exceptions to Tech Spec 3.0.4 & Specify Acceptable Time Limit for Completing Missed Surveillance 1999-09-14
[Table view] Category:TEXT-LICENSE APPLICATIONS & PERMITS
MONTHYEARML17300B3301999-09-14014 September 1999 Application for Amends to Licenses NPF-41,NPF-51 & NPF-74, Making Listed Administrative Changes to TS 5.5.2 & TS 5.6.2 Re Primary Coolant Sources Outside Containment & Annual Radiological Environmental Operating Rept ML17313A9541999-05-26026 May 1999 Application for Amends to Licenses NPF-41,NPF-51 & NPF-74, Reducing Spurious Reactor Trip Hazards Associated with Setpoints While Maintaining Plant Protection ML17313A8331999-02-26026 February 1999 Re-issue of Application for Amend to Licenses NPF-41,NPF-51 & NPF-74,re TS 3.5.3,ECCS - Operating,To Extend Completion Time for One Inoperable LPSI Subsystem from 72 Hours to 7 Days ML17313A8301999-02-26026 February 1999 Application for Amends to Licenses NPF-41,NPF-51 & NPF-74, Revising TS 3.5.3, ECCS - Operating, by Extending Completion Time for One Inoperable LPSI Subsystem from 72 Hours to 7 Days ML17313A7091998-12-16016 December 1998 Application for Amends to Licenses NPF-41,NPF-51 & NPF-74, Changing Condition G of TS 3.8.1 to Ensure That Appropriate Actions Will Be Taken to Prevent Double Sequencing of safety-related Loads ML17313A1571997-12-17017 December 1997 Application for Amends to Licenses NPF-41,NPF-51 & NPF-74, Respectively.Amends Change TS 3/4.8.2 & Associated Bases 3/4.8,allowing Replacement of Existing Class 1E,125 Volt Dc Batteries W/Low Specific Gravity Cell Batteries ML17312B6391997-08-28028 August 1997 Application for Amend to License NPF-51,allowing one-time Extension of Required Surveillance Interval for Msi Sys Portion Only of ESFAS Logic ML17312B4651997-05-23023 May 1997 Rev to 950418 Application for Amends to Licenses NPF-41, NPF-51 & NPF-74,revising TS Section 3/4.4.4, Steam Generators & Associated Bases to Allow Installation of Tube Sleeves as Alternative to Plugging Defective SG Tubes ML17312B1541996-12-27027 December 1996 Application for Amends to Licenses NPF-41,NPF-51 & NPF-74 to Revise TS LCO 3.6.1.3.b of TS 3/4.6.1.3, Containment Air Locks, Bases 3/4.6.1.4, Internal Pressure & 3/4.6.1.6, Containment Structural Integrity. ML17312A8431996-06-28028 June 1996 Application for Amends to Licenses NPF-41,NPF-51 & NPF-74, Amending TS 3/4.5.2, ECCS Subsystems-Operating & Bases to Change SRs 4.5.2.d.2 & 4.5.2.d.3 to Reflect Design Basis Requirements for Anhydrous Trisodium Phosphate ML17300B2631996-06-17017 June 1996 Application for Amends to Licenses NPF-41,NPF-51 & NFP-74, Respectively,Changing Sections 1.10 & 3.2.8 & Associated Bases for Obtaining Thyroid Dcf Used in Definition of Dose Equivalent I-131 ML17312A6471996-04-0101 April 1996 Application for Amend to License NPF-51,revising TS 3/4/9.6 to Temporarily Allow Use of Hoist Instead of Refueling Machine for Movement of Fuel Assembly at Core Location A-07 ML17312A6381996-03-26026 March 1996 Application for Amend to License NPF-51,revising TS 3/4.9.6 to Increase Refueling Machine Overload Cut Off Limit to 2,000 Lb in Effort to Free Stuck Fuel Assembly from Core Location A-06 ML17312A6301996-03-26026 March 1996 Application for Amend to License NPF-51,revising TS 3/4.9.6 to Relocate Refueling Machine Overload Cut Off Limit from TS 3/4.9.6 to Plant UFSAR Per Criteria in 10CFR50.36 & Rev 1 of NUREG-1432, STS for Combustion Engineering Plants. ML17312A6331996-03-23023 March 1996 Application for Amend to License NPF-51,revising TS SR 4.8.2.1.e, DC Sources, to Suspend Provision of TS 4.0.1 & 4.0.4 for Battery Capacity Testing Requirements Until Entry Into Mode 4 Following Sixth Refueling Outage ML17312A6251996-03-22022 March 1996 Application for Amends to Licenses NPF-41,NPF-51 & NPF-74, Modifying TS 3/4.8.1 for Purposes of Implementing Recommended Changes from NUREG-1432,GL 94-01 & GL 96-05 ML17312A5411996-02-0909 February 1996 Suppl Application for Amends to Licenses NPF-41,NPF-51 & NPF-74,implementing New Option B to 10CFR50,App J, Primary Reactor Containment Leakage Testing for Water-Cooled Power Reactors. ML17312A5221996-02-0101 February 1996 Application for Amends to Licenses NPF-41,NPF-51 & NPF-74, Respectively,Changing TS Sections 2.2.1 (Table 2.2-1) & 3/4.3.2 (Tables 3.3-3 & 4.3-2) to Specify Addl Restriction for Allowed Low Pressurizer Pressure Trip Setpoint ML17311B3131995-12-19019 December 1995 Application for Amends to Licenses NPF-41,NPF-51 & NPF-74, Revising TS for Implementation of 10CFR50,App J,Option B for Determining Test Frequency for Containment Leakage Rate Testing ML17311B2651995-11-0707 November 1995 Application for Amend to Licenses NPF-41,NPF-51 & NPF-74, Adopting Approved STS Format & Content of Section 5.0, Design Features, as Modified by Approved Changes to Improved STS ML17311B0931995-08-0303 August 1995 Application for Amends to Licenses NPF-41,NPF-51 & NPF-74, Adding Listed Analytical Method & Associated NRC SER to TS 6.9.1.10, Colr. Prorpietary PVNGS-3 Cycle 6 ECCS Performance Analysis Encl.Proprietary Analysis Withheld ML17311A9501995-06-13013 June 1995 Application for Amends to Licenses NPF-41,NPF-51 & NPF-74, Revising TS Sections 3.5.1,3.5.2,3.7.11,3/4.8.1.1 & Bases to Extend AOTs for Sit,Lpsi Subtrain & EDG & Adding Bases for Extended Aots,Consistent w/NUREG-1366 & GL 93-05 ML17311A8631995-05-0202 May 1995 Application for Amends to Licenses NPF-41,NPF-51 & NPF-74, Revising TS 3.1.2.6,Figure 3.1-1, Min Borated Water Vols by Relocating Plant Elevations That Correspond to Min Required Water Vols for Spent Fuel Pool to Site Procedures ML17311A7531995-03-31031 March 1995 Application for Amends to Licenses NPF-41,NPF-51 & NPF-74. Amends Would Clarify Shutdown Margin Definition,Change shut- Down Margin Applicability & SRs to Comply W/Safety Analysis Assumptions for Subcritical Inadvertent CEA Withdrawal ML17311A5611994-12-28028 December 1994 Application for Amends to Licenses NPF-41,NPF-51 & NPF-74, Revising TS Sections 3.9.6 & 4.9.6.1 Re Refueling Machine Overload Cut Off Limit ML17311A4901994-12-0707 December 1994 Application for Amends to Licenses NPF-41,NPF-51 & NPF-74, Requesting TS 3/4.7.5 to Change Bases for Ultimate Heat Sink from Providing 27 Day Cooling Water Supply to Providing 26 Day Cooling Water Supply ML17311A4481994-11-30030 November 1994 Application for Amends to Licenses NPF-41,NPF-51 & NPF-74, Revising LCO 3.2.1 & 3.2.4 & Associated Bases ML17311A4241994-11-22022 November 1994 Application for Amend to License NPF-41,proposing TS Section 3/4.7.1 by Adding Note to Table 3.7.2 ML17310B4491994-07-12012 July 1994 Application for Amends to Licenses NPF-41,NPF-51 & NPF-74, Requesting Amend to TS Table 3.3-3, ESF Actuation Sys Instrumentation. ML17310B4341994-06-17017 June 1994 Application for Amends to Licenses NPF-41,NPF-51 & NPF-74, Increasing Min Nitrogen Accumulator Pressure ML17310B4071994-06-17017 June 1994 Application for Amend to License NPF-41,NPF-51 & NPF-74 Proposing Ts,By Removing Five Tables of Component Lists, Per GL 91-08 ML17310B2691994-05-0404 May 1994 Application for Amends to Licenses NPF-41,NPF-51 & NPF-74, Clarifying TS LCO 3.4.8.3 & Surveillance Requirement 4.4.2.3.1 Applicability During Steady State Conditions in RCS Heatup/Cooldown Evolutions ML17310B1641994-03-28028 March 1994 Application for Amends to Licenses NPF-41,NPF-51 & NPF-74, Changing Min Condensate Storage Tank Indicated Level from 25 Ft to 29.5 Ft ML17310B0591994-02-18018 February 1994 Application for Amends to Licenses NPF-41,NPF-51 & NPF-74, Revising TS Figure 3.2-1 for Units 1 & 3 & TS 3/4.1.1.4 & Bases 3/4.1.1.4 for Units 1,2 & 3 to Allow Units 1 & 3 to Operate at 100% Full Power Under Reduced Temp Regimen ML17310A8861994-01-0404 January 1994 Application for Amends to Licenses NPF-41,NPF-51 & NPF-74 Modifying Ts,Implementing Recommended Changes from GL 93-05, Line -Item TS Improvements to Reduce SR for Testing During Power Operation. ML17310A8891994-01-0404 January 1994 Application for Amends to Licenses NPF-41,NPF-51 & NPF-74, Proposing Changes to TS Section 3/4.2.3, Azimuthal Power Tilt, & Bases,Requesting Toprovide More Restrictive Azimuthal Power Tilt Limit When COLSS Out of Svc ML17310A8821993-12-30030 December 1993 Application for Amends to Licenses NPF-41,NPF-51 & NPF-74, Changing TS Section 3/4.3.2 by Modifying Tables 3.3-4,3.3-5 & Adding Figure 3.3-1 ML17310A8491993-12-0202 December 1993 Application for Amends to Licenses NPF-41,NPF-51 & NPF-74 Modifying TS by Removing Schedular Requirements for Type a Test to Be Performed Specifically at 40 + or - 10 Month Intervals ML17310A7871993-11-0505 November 1993 Application for Amend to License NPF-51,revising LCOs 3.5.2, ECCS, 3.6.2-1, CSS, 3.7.1.2, Afs, 3.7.3, EWS, 3.7.6, Ecw Sys & 3.7.11, Sdcs Under Exigent Circumstances ML17310A7251993-10-27027 October 1993 Application for Amends to Licenses NPF-41,NPF-51 & NPF-74, Revising TS Section 1.18,6.9.1.8,6.14.c & 6.15.1 in Order to Implement Revised 10CFR50.36a Regulation That Now Allows Radioactive Effluent Release Rept to Be Submitted Annually ML17310A6131993-09-0808 September 1993 Application for Amend to License NPF-41,requesting TS Section 6.9.1.10 to Add Analytical Method Suppl Entitled Sys 80 Inlet Flow Distribution to List of Methods Used to Determine Core Operating Limits ML17310A5181993-08-0505 August 1993 Application for Amends to Licenses NPF-41,NPF-51 & NPF-65, Requesting Change to Word Pressurizer to RCS for Item 4 in Tables 3.3-10 & 4.3-7 ML17310A4181993-06-30030 June 1993 Application for Amends to Licenses NPF-41,NPF-51 & NPF-74, Revising TS 3/4.3.2 to Request Addl Operating Margin in Time Response of Turbine Driven AF Pump to SG Low Level Signal ML17306B1981992-12-28028 December 1992 Application for Amends to Licenses NPF-41,NPF-51 & NPF-74, Respectively,Revising TS 3/4.3.1,Table 4.3-1 & 3/4.3.2,Table 4.3-2,to Change Surveillance Requirements from Monthly to Quarterly for Several Channel Functional Tests ML17306A6891992-04-27027 April 1992 Application for Amends to Licenses NPF-41,NPF-51 & NPF-74, Amending Tech Spec 3/5.7.6 & Bases of Section 3/4.7.6 to Reduce Essential Chilled Water Sys out-of-svc Time from 7 Days to 72 H ML17306A6091992-03-20020 March 1992 Application for Amends to Licenses NPF-41,NPF-51 & NPF-74, Revising TS Section 3/4.9.9 to Change Containment Purge Valve Isolation Sys Operability Requirements for Consistency W/Other Containment Penetration Operability Requirements ML17306A3761991-12-30030 December 1991 Application for Amends to Licenses NPF-41,NPF-51 & NPF-74, Revising TS Section 3.6.1.7 Action Statements Re Containment Purge Supply & Exhaust Valves for Consistency W/Other Containment Sys Action Requirements ML17306A3541991-12-20020 December 1991 Application for Amend to License NPF-74,adding Sentence to TS Section 5.3.1 to Allow Substitution of Up to Total of 80 Fuel Rods Clad W/Advanced zirconium-based Alloys Other than Zircaloy-4 in Two Fuel Assemblies.Rept Withheld ML17305B7301991-09-0909 September 1991 Application for Amends to Licenses NPF-41,NPF-51 & NPF-74, Changing Tech Spec 3/4.7.11, Shutdown Cooling Sys to Delete auto-closure Interlock Surveillance of Surveillance Requirement 4.7.11b,per Generic Ltr 88-17 ML17305B7161991-08-28028 August 1991 Application for Amends to Licenses NPF-41,NPF-51 & NPF-74. Proposed Amends Resolve Inconsistent Application of Exceptions to Tech Spec 3.0.4 & Specify Acceptable Time Limit for Completing Missed Surveillance 1999-09-14
[Table view] |
Text
REGULA INFORMATION DISTRIBUTION YSTEM (RIDS)
~ I ACCESSION NBR: 8801200451 DOC. DATE: 88/01/14 NOTARIZED: NO DOCKET 0 FACIL: STN-50-529 Palo Verde Nuclear Stationi Unit 2I Arizona Publi 05000529 AUTH. NAME AUTHOR AFFILIATION VAN BRUNT'. E. Arizona Nuclear Pacer Prospect (formerly Arizona Public RECIPIENT AFFILlATION Serv'ECIP.
NAME Document ContT ol Branch (Document Control 'esk )
SUBJECT:
Application for amend to License NPF-5iI permitting one-time onlg exception to Surveillance Requirements 4. 4. 10 to allow RCS vent valve RCB-HV-105 to be tested during Node 3 operations instead of- current Mode 5 or 6. Fee paid.
DISTRIBUTION CODE: NOOSD COPIES RECEIVED: LTR i ENCL l SIZE:
TITLE: License Fees NOTES: Standardized plant. 05000529 REC IP IENT COP IES RECIPIENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL PD5 LA 1 0 PD5 PD 1 1 LICITR*IE DAVISI N 1 1 INTERNAL: ARM/D*F/LFMB 1 1 FIL 01 1 1 EXTERNAL: LPDR 1 NRC PDR 1 1 NOTES:
TOTAL NUMBER OF COPIES REGUlRED: LTTR 9 ENCL 8
~ ~
j n
ilt Arizona Nuclear Power Project P.O. BOX 52034 ~ PHOENIX, ARIZONA85072-2034 161-00743-EEVB/BJA January 14, 1988 Docket No. STN 50-529 U. S. Nuclear Regulatory Commission Washington, D. C. 20555 Attention: Document Control Desk
Dear Sirs:
Subject:
Palo Verde Nuclear Generating Station (PVNGS)
Unit 2 Proposed Technical Specification Change-One Time Exception to Surveillance Requirement for Valve RCB-HV-105 File: 88-F-056-026; 88-F-005-419.05 The purpose of this letter is to request a change to the PVNGS Unit 2 Technical Specifications. Specifically, the proposed change provides for a one-time only exception to the surveillance requirements for Reactor Coolant System (RCS) vent valve RCB-HV-105. Technical Specification Surveillance Requirement 4.4.10 currently requires the RCS vent valves to be tested at least once every 18 months when in Modes 5 or 6. Valve RCB-HV-105 was last tested in November, 1987 during an unplanned reactor shutdown. The surveillance test of the valve was acceptable and did not result in any adverse impact on plant safety. However, Unit 2 was in Mode 3 during the performance of this test. The proposed change will allow ANPP to credit this surveillance test for satisfying Surveillance Requirement 4.4.10. From previous conversations with the NRC staff, it is our understanding that this change request does not need prior approval to allow for continued operation of PVNGS Unit 2 until the first refueling outage. The justification for this proposed change is provided in the attachment to this letter along with the following information:
A. Description of the Proposed Change.
B. Purpose of the Technical Specification.
C. Need for the Technical Specification Amendment.
D. Basis for No Significant Hazards Consideration Determination.
E. Safety Evaluation for the Proposed Change.
F. Environmental Impact Consideration Determination.
G. Marked-up Technical Specification Change Page.
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0 USNRC Doc~ynt Control Desk 161-00743-EEVB/BJA Page 2 January 14, 1988 Pursuant to the requirements of 10CFR50.91(b)(1), and by copy of this letter, we have notified the Arizona Radiation Regulatory Agency of this request for a Technical Specification change. In accordance with the requirements of 10CFR170.12(c), the license amendment application fee of $ 150.00 has been forwarded to the Facilities Program Coordinator of LBB.
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E. E. Van Brunt, Jr.
Executive Vice President Project Director EEVB/BJA/ls Attachment cc: 0. M. De Michele (all w/a)
G. W. Knighton E. A. Licitra J. R. Ball J. B. Martin Director, ARRA A. C. Gehr R. M. Diggs (w/WFD $ 150)
Jahuary 26, 1988 NOTE FOR: Jim McKnight Document Control Desk (016)
FROM: Jane Parks License Fee Management Branch, ANI/DAF
SUBJECT:
PROCESSING LETTERS WITH CHECKS RECEIVED DIRECTLY BY THE LICENSE FEE MANAGEMENT BRANCH Please process the enclosed letter under the applicable docket and give the following distribution under code M008:
Original of ltr to Regulatory Docket File Action cy w/check to C. J. Holloway, LFMB (AR-2015) 3 cys to applicable branch of DL 1 cy to LPDR 1 cy to PDR I am retaining the check, and the following information is for your reco'rds:
Check No.:
Amount: $ 150 Date: 1/18/88 Ltr Date: 1/14/88 Appl i cant Arizona Publ i c Serv i ce Co.
Docket No.:
Plant: Palo Verde 2 Thank you for your cooperation.
Ja e Parks
@cense Fee Management Branch Division of Accounting and Finance Office of Admi.nistration and Resources Management
Enclosure:
Ltr. dtd 1/14/88
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REGULAT INFORMATION DIBTRIBUTIQ YSTEM (RIDS>
j ACCESSION NBR: 8801200451 DOC. DATE: 88/01/14 NOTARIZED: NO DOCKET 0 FACIL: STN-50-529 Pa)o Verde Nuclear Stations Unit 2> Arizona Publi 0500052'P AUTH. NAME AUTHOR AFFILIATION VAN BRUNTI E. E. Arizona Nuclear Poujer Prospect ( formerly Arizona Public Serv RECIP. NAME RECIPIENT AFFILIATION Document Control Branch (Document Control Desk)
SUBJECT:
Application for amend to License NPF-51 permitting one-time only exception to Surveillance Requirements 4. 4. 10 to allouj RCS vent valve RCB-HV-105 to be tested during Mode 3 operations instead of currently required Mode 5 or h.
DISTR ISUTIDN CODE: AOOID COPIES RECEIVED: LTR Q ENCL g SIZE: 7+/
TITLE: OR Submittal: General Distribution NOTES: Standardized plant. 0500052'P REC IP IENT -
COPIEB RECIPIENT COPIEB ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL PD5 LA 1 0 PD5 PD 5 5 LICITRAIE 1 1 DAVIBIM 1 1 INTERNAL: ACRB 6 6 ARM/DAF/LFMB 1 0 NRR/DEBT/ADB 1 NRR/DEBT/CEO 1 1 NRR/DEBT/MTB NRR/DEBT/RSB Q~,
1 1 1 1 NRR/DOEA/TBB 1 1 NRR/ ILRB 1 OGC/HDS1 0 01 1 1 REB/DE/EIB 1 1 EXTERNAL: LPDR 1 1 NRC PDR 1 1 NBIC 1 1 NOTES: 1 1 TOTAL NUMBER OF COPIES REQUIRED: LTTR 28 ENCL 25
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Arizona Nuclear Power Project P,O. BOX 52034 ~ PHOENIX. ARIZONA85072-2034 161-00743-EEVB/BJA January 14, 1988 Docket No. STN 50-529 U. S. Nuclear Regulatory Commission Washington, D. C. 20555 Attention: Document Control Desk
Dear Sirs:
Subject:
Palo Verde Nuclear Generating Station (PVNGS)
Unit 2 Proposed Technical Specification Change-One Time Exception to Surveillance Requirement for Valve RCB-HV-105 File: 88-F-056-026; 88-F-005-419.05 The purpose of this letter is to request a change to the PVNGS Unit 2 Technical Specifications. Specifically, the proposed change provides for a one-time only exception to the surveillance requirements for Reactor Coolant System (RCS) vent valve RCB-HV-105. Technical Specification Surveillance Requirement 4.4.10 currently requires the RCS vent valves to be tested at least once every 18 months when in Modes 5 or 6. Valve RCB-HV-105 was last tested in November, 1987 during an unplanned reactor shutdown. The surveillance test of the valve was acceptable and did not result in any adverse impact on plant safety. However, Unit 2 was in Mode 3 during the performance of this test. The proposed change, will allow ANPP to credit this surveillance test for satisfying Surveillance Requirement 4.4.10. From previous conversations with the NRC staff, it is our understanding that this change request does not need prior approval to allow for continued operation of PVNGS Unit 2 until the first refueling outage. The justification for this proposed change is provided in the attachment to,this letter along with the following information:
A. Description of the Proposed Change.
B. Purpose of the Technical Specification.
C. Need for the Technical Specification Amendment.
D. Basis for No Significant Hazards Consideration Determination.
E. Safety Evaluation for the Proposed Change.
F. Environmental Impact Consideration Determination.
G. Marked-up Technical Specification Change Page.
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USNRC Document Control Desk 161-00743-EEVB/BJA Page 2 January 14, 1988 Pursuant to the requirements of 10CFR50.91(b)(l), and by copy of this letter, we have notified the Arizona Radiation Regulatory Agency of this request for a Technical Specification change. In accordance with the requirements of 10CFR170.12(c), the license amendment application fee of $ 150.00 has been forwarded to the Facilities Program Coordinator of LFMB.
Very truly your
- c. 4m E. E. Van Brunt, Jr.
Executive Vice President Project Director EEVB/BJA/ls Attachment cc: 0. M. De Michele (all w/a)
G. W. Knighton E. A. Licitra J. R. Ball J. B. Martin Director, ARRA A. C. Gehr R. M. Diggs (w/WFD $ 150)
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ATTACHMENT A. DESCRIPTION OF THE PROPOSED CHANGE This proposed Technical Specification change allows for a one-time only exception to Surveillance Requirement 4.4.10 to allow RCS vent valve RCB-HV-105 to be tested, during Mode 3 operations instead of the currently required Modes 5 or 6.
Technical Specification Limiting Condition for Operation (LCO) 3.4.10 requires the RCS vent paths to be operable during Modes 1 through 4. The 'associated Surveillance Requirement 4.4.10 specifies that each RCS vent path shall be demonstrated operable at least once every 18 months when in Modes 5 or 6 by cycling each vent valve from the control room and by verifying flow through each RCS vent path.
~ - Valve RCB-HV-105 was last tested in November, 1987 during an unplanned reactor shutdown. However, Unit 2 was in Mode 3 during the performance of this test.
The test was conducted in a manner such that the safety of the plant would not be compromised during the testing. The test method took advantage of the fact that the line upstream of valve RCB-HV-105 had been partially 'pressurized due to a slight leak from one of the upstream valves. Valve RCB-HV-105 was then cycled from the control room while verifying that the upstream pressure decreased as the upstream line was vented to the Reactor Drain Tank (RDT).
This test method allowed for testing valve RCB-HV-105 without jeopardizing the integrity of the RCS since the upstream valves remained closed during the testing. The proposed change will allow ANPP to credit this previously conducted test on the valve to satisfy Surveillance Requirement 4.4.10.
PURPOSE OF THE TECHNICAL SPECIFICATION Technical Specification LCO 3.4.10 and related Surveillance Requirement 4.4.10 ensure that the RCS vent system is available to perform its required function.
As stated in Technical Specification bases section 3/4.4.10, the RCS vents are provided to exhaust non-condensible gases and/or steam from the RCS that could inhibit natural circulation core cooling. Some additional functions of the system that are not specifically discussed in the Technical Specification bases are to: 1) provide a means of collapsing a steam void in the reactor vessel upper head region during a natural circulation cooldown, and 2) provide a means of raising pressurizer level during a Steam Generator Tube Rupture (SGTR) accident so that the safety injection throttling criteria can be met.
The RCS vent system is shown in Figure 1. The system provides redundant vent paths from the pressurizer steam space and from the reactor vessel upper head.
The vented gases and/or steam can then be directed to either the RDT or the containment atmosphere. The system is composed of seven solenoid operated valves that can be operated remotely from the main control room. The system was installed in the PVNGS units in response to TMI item II.B.1. For further discussion of the system design refer to section 18.II.B.l of the PVNGS FSAR.
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C. NEED FOR THE TECHNICAL SPECIFICATION AMENDMENT The surveillance test for valve RCB-HV-105 has already been conducted. The test was successfully conducted in November, 1987 while Unit 2 was in an unplanned reactor shutdown. Surveillance Requirement 4.4.10 specifies that the unit must be in Modes 5 or 6 during the performance of the vent valve testing. This proposed change will allow ANPP to credit this Mode 3 surveillance test for satisfying Surveillance Requirement 4.4.10.
BASIS FOR NO SIGNIFICANT HAZARDS CONSIDERATION The Commission has provided standards for determining whether a significant hazards consideration exists as stated in 10CFR50.92. A proposed amendment to an operating license for a facility involves a no significant hazards consideration if operation of the facility in accordance with a proposed amendment would not: (1) involve a significant increase in the probability or consequences of an accident previously evaluated; or (2) create the possibility of a new or different kind of accident from any accident previously evaluated; or (3) involve a significant reduction in a margin of safety. A discussion of these standards as they relate to the amendment'equest follows:
Standard 1--Involve a significant increase in the probability or consequences of an accident previously evaluated.
Basis- The proposed Technical Specification change does not involve a significant increase in the probability or'onsequences of an accident previously evaluated. For this proposed change, the main accident of concern is a Loss of Coolant Accident (LOCA) as a result of two stuck open vent valves during the testing. As described in FSAR section 18.II.B.l, the RCS vent system is designed in accordance with 10CFR50.46 in that the RCS vent paths are provided with 7/32" orifices to limit the flow from an unisolable leak. CESSAR section 9.3.4.1.2 states that a single charging pump has a capacity sufficient to replace the flow lost due to leaks in small RCS lines (i.e., lines with 7/32" by 1" long flow restricting devices). Therefore, a LOCA event will not result from the testing and the probability of having a LOCA event remains unchanged.
The consequences of a vent valve failure also remain unchanged. In the unlikely event that two vent valves in series fail to open, a single charging pump has sufficient capacity to replace the coolant lost through the unisolable vent path. The likelihood of an unisolable vent path during this test of vent valve RCB-HV-105 is further reduced by only cycling this valve during the testing. This maintains the upstream vent valves closed to prevent an unisolable vent path.
Standard 2--Create the possibility of a new or different kind of accident from any accident previously analyzed.
Basis- The proposed change allows for testing valve RCB-HV-105 during Mode 3 operations instead of the Technical Specification required Modes 5 or 6. The possible malfunctioning/accident that could result from this test is the failure of valve RCB-HV-105 to close. This could lead to an unisolable RCS vent path if one of the upstream valves was opened during the test and it also failed to close. This type of malfunction has been
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ft evaluated in the FSAR. The malfunction will not lead to a LOCA since the anticipated coolant loss will be within the makeup capacity of a single charging pump. Therefore, this Technical Specification change will not create the possibility of a new or different kind of accident from any accident previously analyzed.
Standard 3--Involve a significant 'reduction in a margin of safety.
Basis Technical Specification bases section 3/4.4.10 discusses the RCS vents. This bases section states, "The valve redundancy of the Reactor Coolant System vent paths serves to minimize the probability of inadvertent or irreversible actuation while ensuring that a single failure of a vent valve, power supply, or control system does not prevent isolation of the vent path." If a vent path were established in Mode 3 by opening two vent valves in series, a single failure of one of the valves to close would not result in an unisolable vent path. Therefore, this proposed change will not result in a reduction in a margin of safety.
- 2. The Commission has provided guidance concerning the application of the standards for determining whether a significant hazards consideration exists by providing certain examples (51FR7751) of amendments that are considered least likely to involve a significant hazards consideration.
This proposed amendment does not match any of the examples provided by the Commission. However, this change can be described as a change to a Surveillance Requirement where the results of the change are clearly within all acceptable criteria for the system. The RCS vent system was designed to be operated over a wide variety of RCS pressure and temperature conditions including Mode 3 conditions. Therefore, operation of a vent valve for testing while in Mode 3 is in accordance with the system design.
SAFETY EVALU T ON FOR THE PROPOSED CHANGE This proposed Technical Specification change will not increase the probability or consequences of any accident previously evaluated.'he primary accident of concern for this proposed Technical Specification change is a LOCA due to stuck open vent valves during the surveillance test. Note that you would need at least two vent valves in series stuck open to result in an unisolable vent path. As discussed in FSAR section 18.II.B.1, the RCS vent system is designed in accordance with 10CFR50 46. Paragraph (c) of 10CFR50.46 defines a LOCA as
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a hypothetical accident that would result from a loss of reactor coolant at a rate in excess of the capability of the reactor coolant makeup system. Each reactor coolant system vent (except for the 1" vent line with double instead of single valves) is provided with a 7/32" orifice to limit the flow from an unisolable leak. As stated in CESSAR section 9.3.4.1.2, one charging pump has a capacity sufficient to replace the coolant lost due to leaks in small RCS lines (lines with 7/32" x 1" long flow restricting devices.) Therefore, even if a RCS vent path was unisolable during performance of this surveillance test, it would not result in a loss of reactor coolant in excess of the makeup capacity of a single charging pump and would not result in a LOCA. Likewise, the consequences of an unisolable vent path would not be a serious detriment to plant safety since the lost coolant can easily be replaced by the charging system.
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e The proposed Technical Specification change will not create the possibility of an accident or a malfunctioning of a different type than any evaluated previously in the FSAR. This change involves a one-time only exception to Surveillance Requirement 4.4.10 which will allow for testing valve RCB-HV-105 during Mode 3 operations instead of the currently required Modes 5 or 6. The potential malfunctioning/accident that could result from this test is the failure of valve RCB-HV-105 to close. The test method used for this Mode 3 test ensures that the failure of valve RCB-HV-105 to close will not result in an unisolable vent path. This is because the upstream vent valves remained closed during the test. Therefore, no new accident scenarios are created by this test. This proposed change will not result in a reduction in a margin of safety as defined in the basis for any Technical Specification. Bases section 3/4.4.10 discusses the RCS vents. The bases section states that, "The valve redundancy of the Reactor Coolant System vent paths serves to minimize the probability of inadvertent or irreversible actuation while ensuring that a single failure of a vent valve, power supply, or control system does not prevent isolation of the vent path," Therefore, if a vent path were established in Mode 3 by opening two vent valves in series, a single failure of one of the valves to close would not result in an unisolable vent path.
F. ENVIRONMENTAL IMPACT CONSIDERATION DETERMINATION The proposed Technical Specification change request does not involve an unreviewed environmental question because operation of PVNGS Unit 2 in accordance with this change would not:
- 1. Result in a significant increase in any adverse environmental impact previously evaluated in the Final Environmental Statement (FES) as modified by the staff's testimony to the Atomic Safety and Licensing Board (ASLB), Supplements to the FES, Environmental Impact Appraisal, or in any decisions of the ASLB; or
- 2. Result in matters not previously reviewed in the licensing basis for PVNGS which may have a significant environmental impact, MARKED-UP TECHNICAL SPECIFICATION CHANGE PAGES Enclosed is revised page 3/4 4-35 of the PVNGS Unit 2 Technical Specifications. s
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