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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
CATEGORY 1 REGULAT Z INFORMATION DISTRIBUTION YSTEM (RIDS)
ACCESSION NBR:9607100202 DOC.DATE: 96/06/28 NOTARIZED: YES DOCKET FACIL:STN-50-528 Palo Verde Nuclear Station, Unit 1, Arizona Publi 05000528 STN-50-529 Palo Verde Nuclear Station, Unit 2, Arizona 05000529 Palo Verde Nuclear Station, Unit 3, Arizona Publi Publi'TN-50-530 05000530 AUTH. NAME AUTHOR AFFILIATION STEWART,W.L. Arizona Public Service Co. (formerly Arizona Nuclear Power RECIP.NAME RECIPIENT AFFILIATION Document Control Branch (Document Control Desk)
SUBJECT:
Application for amends to licenses NPF-41 NPF-51 & NPF-74, re TS 3/4.5.2,changing SRs 4.5.5.d.2 & 4.5.2.d.3 to -reflect design basis requirements for anhydrous TSP utilized in containment following LOCA.
DISTRIBUTION CODE: ZOOID COPIES RECEIVED:LTR 1 ENCL i SIZE: I! E TITLE: OR Submittal: General Distribution G
NOTES:STANDARDIZED PLANT 05000528 Standardized plant. 05000529 Standardized plant. 05000530 RECIPIENT COPIES RECIPIENT COPIES Y ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL PD4-2 LA 1 1 PD4-2 PD 1 1 CLIFFORD,J 1 1 CLIFFORDEJ. 1 ~ 1 ZNTERNAL: ACRS 1 1 01 1 . 1
'RR/DE/EMCB 1 1 NRR/DRCH/HICB 1 1 NRR/DSSA/SPLB 1 1 NRR/DSSA/SRXB 1 1 NUDOCS-ABSTRACT 1 1 OGC/HDS2 1 0 0
EXTERNAL: NOAC 1 1 NRC PDR 1' N
NOTE TO ALL "RZDS" RECIPIENTS:
PLEASE HELP US TO REDUCE WASTETH CONTACT THE DOCUMENT CONTROL DESK)
ROOM OWFN SD-5(EXT. 415-2083) TO ELZMZNATE YOUR NAME FROM DISTRIBUTION LISTS FOR DOCUMENTS YOU DON'T NEED!
TOTAL NUMBER OF COPIES REQUIRED: LTTR 0
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10 CFR 50.90 Arizona Public Service PALO VERDE NUCLEAR GENERATING STATION P.O. BOX 52034 PHOENIX, ARIZONA 85072-2034 WILLIAML. STEWART EXECUTIVE VICE PRESIDENT 102-03727-WLS/A KK/NLT NUCLEAR June 28, 1996 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Mail Station P1-37 Washington, DC 20555-0001
Dear Sirs:
Subject:
Palo Verde Nuclear Generating Station (PVNGS)
Units 1,2, and 3 Docket Nos. STN 50-528/529/530 Proposed Amendment to Technical Specification (TS)
Section 3/4.5.2, "ECCS Subsystems-Operating" and the Associated Bases Pursuant to 10 CFR 50.90, Arizona Public Service Company (APS) submits herewith a proposed amendment to Technical Specification (TS) Section 3/4.5.2, "ECCS Subsystems-Operating," and the associated bases. The proposed amendment to TS 3/4.5.2 would change the Surveillance Requirements (SR) 4.5.2.d.2 and 4.5.2.d.3 to reflect the design basis requirements for anhydrous trisodium phosphate (TSP) which is utilized in containment following a loss-of-coolant accident (LOCA) to ensure the borated water is adjusted to a pH of > 7.
Provided in the enclosure to this letter are the following:
A. Description of the Proposed Amendment B. Purpose of the Technical Specification C. Need for the Technical SpeciTication Amendment D. Safety Analysis of the Proposed Technical Specification Amendment No Significant Hazards Consideration Determination Environmental Consideration G. Marked-up Technical Specification Change Pages In accordance with TS Section 6.5, the Plant Review Board and Offsite Safety Review Committee have reviewed and concur with this proposed amendment. Pursuant to 10 CFR 50.91(b)(1), a copy of this request has been forwarded to the Arizona Radiation Regulatory Agency.
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0 f U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Proposed Amendment to TS Section 3/4.5.2 and Associated Bases Page 2 Approval of this proposed amendment is requested by November 1, 1996, in order to support the performance of the surveillance test prior to the startup of PVNGS Unit 1 Cycle 7 from refueling outage 6. It is requested that this proposed amendment become effective within 45 days of issuance by the NRC for PVNGS Units 1, 2, and 3.
Should you have any questions, please contact Scott A. Bauer at (602) 393-5978.
Sincerely, WLS/AKK/NLT/pv Enclosure cc: L. J. Callan K. E. Perkins J. W. Clifford K. E. Johnston '.
V. Godwin (ARRA)
STATE OF ARIZONA )
) ss.
COUNTY OF MARICOPA )
I, W. L. Stewart, represent that I am Executive Vice President - Nuclear, Arizona Public Service Company (APS), that the foregoing document has been signed by me on behalf of APS with full authority to do so, and that to the best of my knowledge and belief, the statements made therein are true and correct.
W. L. Stewa Sworn To Before Me This 28 Day Of JSNre, 1996.
Notary Public 5
My Commission Expires My Commffslon Exp'Iirs June %2,'l9N
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ENCLOSURE PROPOSED AMENDMENTTO TECHNICAL SPECIFICATION SECTION 3/4.5.2, "ECCS SUBSYSTEMS-OPERATING,"
AND THE ASSOCIATED BASES
A. DESC IO OF THE PROPOSED ME DME The proposed amendment to Technical Specification (TS) 3/4.5.2, "ECCS Subsystems-Operating," Surveillance Requirements (SR) 4.5.2.d.2 and 4.5.2.d.3 would change the specifications associated with trisodium phosphate (TSP) to reflect that which is actually loaded and required in containment to ensure that borated water is adjusted to a pH of > 7 during post-loss-of-coolant accident (LOCA) conditions. Additionally, a clarification to the associated bases is proposed.
Design basis calculations have been re-performed to determine the actual anhydrous TSP volume and surveillance concentration required, based on maximum post-LOCA containment water volumes and the actual density of anhydrous TSP installed in the units, to ensure post-LOCA containment solution pH > 7. Specifically, SR 4.5.2.d.2 would change to increase the minimum required amount of solid granular anhydrous TSP in the TSP storage baskets from "464" to "524" ft'o meet the new design basis requirement.
SR 4.5.2.d.3 would change from "0.055 a 0.001 lb. of TSP submerged in 1.0 a 0.05 gallons of 77 a 9'F borated water" to "3.5 a 0.005 grams of anhydrous TSP (corrected for moisture content) submerged in 1.0 a 0.005 liter of 2.5 wt% boric acid solution (nominally 4400 ppm boron) at 135 a 9'F." The SR would still specify that the pH of the solution as measured at 77 a 9'F is raised to > 7 within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.
Bases Section 4.5.2 and 4.5.3 would be reworded to remove reference to the term "dissolving baskets" and replace it with verbiage which clearly states how the TSP is stored and utilized. Specifically, it is proposed that the fourth paragraph of the bases be deleted and replaced with the following:
"Anhydrous TSP is stored in baskets in containment that allow the TSP to dissolve into containment water following a large break LOCA. Once dissolved in the containment sump water, the TSP will increase the water pH to > 7. Maintaining the pH t
at 7 prevents a significant fraction of dissolved iodine from converting to a volatile form and minimizes'the potential of stress corrosion cracking of austenitic stainless steel components in containment following a LOCA."
Additionally, a revision to the bases is proposed to clarify that the TSP sample will be dissolved in a borated water source as opposed to specifying the Refueling Water Tank (RWT) as the borated water source.'age 1 of 7
A U OSE OF EC ICAL SPEC FICATION TS SR 4.5.2.d.2 requires that a specified volume of solid granular TSP be contained in the storage baskets in order to condition the sump water following a LOCA. The required pH of the sump solution is based on the long-term retention of iodine and is sufficient to avoid stress corrosion cracking of austenitic stainless steel and excessive generation of hydrogen by the corrosion of containment metals.
The dissolution rate of the solid form of TSP,is demonstrated by the acceptable performance of the 18-month surveillance test conducted in accordance with TS SR 4.5.2.d.3. This surveillance test verifies dissolution characteristics by demonstrating that a representative sample of the anhydrous material dissolves in borated water without agitation and raises the pH of the water to > 7 within a 4-hour period.
NEED FOR T E EC CAL S ECIFICATION MENDMEN I
Palo Verde Nuclear Generating Station (PVNGS) is in the process of converting the TS for all three units to Revision 1 of NUREG-1432, "Standard Technical Specifications, Combustion Engineering Plants." As part of this conversion process, information contained in the current TS was validated and it was previously identiTied that the form of the TSP in the containment baskets is the anhydrous form rather than the dodecahydrate form. As a result of this discovery a TS change was requested under emergency circumstances and granted by the NRC in Amendments 107, 99, and 79 for Units 1, 2, and 3, respectively.
Subsequently, the engineering review continued, and the design basis calculation was revised which resulted in a higher required concentration of TSP than currently required by TS to ensure the pH requirements of the TS are met. The maximum water volume utilized in the new calculation assumes a volume of water due to flooding from credible water 'sources. The actual bulk density of the anhydrous TSP installed was determined to be lower than that which was assumed in the original design basis calculation and Updated Final Safety Analysis Report (UFSAR) Section 6.1.1.2. Additionally, actual laboratory testing on the installed anhydrous TSP indicated that more TSP is required to neutralize the borated water than determined by the original design basis calculation.
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I The current TS requires a minimum of 464 ft. This equates to approximately 22,450 pounds of anhydrous TSP at a bulk density of 48.4 pounds per cubic foot.
The bulk density of 48.4 pounds per cubic foot has been verified by sampling and laboratory analysis. The total mass of 22,450 pounds, divided by the total post-LOCA sump water inventory of 867,124 gallons, yields an anhydrous TSP concentration of 3.1 grams per liter of containment sump water. Using this analytically defined concentration of 3.1 grams TSP per liter of containment sump water results in a pH less than the required minimum pH of 7. It was determined by laboratory analysis that a sample of 3.5 grams per liter is required to ensure a minimum pH of 7 for the above design conditions and TSP specifications. A concentration of 3.5 grams per liter and a post-LOCA water volume of 867,124 gallons translates to 25,325 pounds or 524 ft of anhydrous TSP. Incorporating a volume of 524 ft of anhydrous TSP in TS SR 4.5.d.2 will ensure that the pH of the post-LOCA solution is > 7. Proposed surveillance test tolerances are based on standard chemistry laboratory practices and quality control measures. Sufficient margin exists in design basis calculations to account for these tolerances.
A change to 4.5.2.d.3 is proposed to clarify how the surveillance test is to be performed. The proposed change specifies that the TSP will be dissolved in 2.5 wt% boric acid solution (nominally 4400 ppm) at 135 a 9'F (the shutdown cooling heat exchanger outlet temperature). The requirement to dissolve the TSP sample at 135 a 9'F provides assurance that the stored TSP will dissolve in borated water at postulated post-LOCA temperatures. Specifying the concentration of boron will ensure that the surveillance test is conservatively performed at the highest possible concentration of available borated water. The determination of pH remains at a temperature of 77 a 9'F.
Bases Section 4.5.2 and 4.5.3 would be reworded to remove reference to the term "dissolving baskets" and replace it with verbiage which clearly states how the TSP is stored and utilized. Additionally, a revision to the bases is proposed to clarify that the TSP sample will be dissolved in a borated water source as opposed to specifying the RWT as the borated water source. This change, coupled with the proposed change to specify the concentration of the boric acid solution in TS SR 4.5.2.d.3, is conservative since RWT boron concentration can vary between 4000 and 4400 ppm in accordance with TS.
D. S E L SIS OF THE OPOSED C CAL S ECIFICATION A~ME 0 E TSP is installed in baskets in the containment building to ensure that iodine, which may be dissolved in the recirculated reactor cooling water following a LOCA, Page 3 of 7
N remains in solution. The TSP acts as a passive form of pH control for post-LOCA containment spray and core cooling water. The dissolution of the TSP in the baskets results in a neutral to slightly alkaline solution which precludes release of volatile iodine into the containment atmosphere during recirculation following a LOCA. Buffering of the borated LOCA inventory also minimizes the effects of chloride and caustic stress corrosion on mechanical systems and components.
The LOCA radiological consequences analysis takes credit for iodine retention in the sump solution based on the recirculation water pH being > 7. The radionuclide releases from the containment atmosphere and the consequences of a LOCA would be incre'ased if the pH of the recirculation water was not adjusted to 7 or above. The proposed TS amendment would revise TS SRs 4.5.2.d.2 and 4.5.2.d.3 to increase the required volume and surveillance test concentration of anhydrous TSP to ensure that the pH requirements of the TS are met.
The amount of TSP required is based on the quantities of borated water that accumulate in the sump and containment fioor following a LOCA. The analyses specific to PVNGS conservatively assume a total flood volume equal to the complete depletion of the Reactor Coolant System, Refueling Water Tank, and Safety Injection Tank inventories and assume a concentration of 4400 ppm boron in the sump solution. This assumption is conservative based on actual flooding analyses and yields greater requirements in terms of required amounts of equivalent TSP. Based on this conservative assessment of the total containment post-LOCA inventory and boron concentration, the required amount of anhydrous TSP is 524 ft . Surveillance tests have been performed which demonstrate that each PVNGS unit currently has in excess of 550 ft installed and the new design basis requirements are currently being met.
The dissolution rate of the anhydrous TSP is demonstrated by the acceptable performance of the 18-month surveillance tests conducted in accordance with TS 4.5.2.d.2 and 4.5.2.d.3. These surveillance tests verify dissolution characteristics by demonstrating that a representative sample of the anhydrous material dissolves in water without agitation and raises the pH of the water to > 7 within a 4-hour period. Dissolving the TSP at a temperature of 135 a 9'F is conservative in that sufficient margin exists since minimum post-LOCA temperatures are assumed to be 300 'F. Additionally, sufficient margin exists in design basis calculations to account for tolerances used when performing surveillance testing.
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E. NOSG C Z DSCO SDE 0 DE E 0 The Commission has provided standards for determining whether a significant hazards consideration exists as stated in 10 CFR 50.92. 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; (2) create the possibility of a new or different kind of accident from any accident previously evaluated; or (3) involve a signiTicant reduction in a margin of safety. A discussion of these standards as they relate to this amendment request follows:
~8d -D th p p d d ti 1 ig it ti i th probability or consequences of an accident previously evaluated?
No. The proposed amendment does not involve any change to-the method of operation of any plant equipment or modify any plant equipment. The proposed amendment is associated with a passive component that mitigates the consequences of a LOCA, and does not contribute to increasing the probability of an accident. The proposed amendment ensures that the correct volumes and mass of anhydrous TSP are utilized such that the post-LOCA ECCS solution is
', maintained at a pH above 7. This ensures that radiological consequences are minimized by preventing significant amounts of iodine released from fuel failures and dissolved in the recirculating water from converting to a volatile form and evolving into the containment atmosphere. Therefore, the proposed amendment does not involve a significant increase in the probability or consequences of an accident.
~DD d 2 D th p p d d t t ih p thtttty t different kind of accident from any accident previously evaluated?
No. The proposed amendment does not modify the configuration of the units, involve any change to plant equipment, or change the method of plant operation other than increase the amount of TSP required to ensure sufficient amounts of anhydrous TSP is available to minimize post-LOCA radiological consequences.
The proposed amendment is associated with a passive component that mitigates the consequences of a LOCA, and no new failure modes have been defined for any plant system or component important to safety. Additionally, no new limiting failures have been identified as a result of the proposed changes. Current structural and'seismic design basis calculations bound this change. Maintaining the solution pH a 7 also reduces the occurrence of stress corrosion cracking (SCC)
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of austenitic stainless steel components in containment. Reducing SCC reduces the probability of failure of components. Therefore, the amendment does not create the possibility of a new or different kind of accident from any accident previously evaluated.
d d g td d d d d tt I tgtt t d margin of safety?
No. The margin of safety is maintained by the use of sufficient amounts of anhydrous TSP to provide the necessary pH control following a LOCA such that iodine, washed to the containment sump by containment spray action, remains in solution and is not released due to acidic conditions. Consequently, iodine concentrations in the containment atmosphere are maintained low and within the concentrations assumed for calculations of off-site dose. Therefore, the amendment does not involve a signiTicant reduction in the margin of safety.
F. ENVI ON E D APS has determined that the proposed amendment involves no change in the amount or type of effluent that may be released offsite, and that there is no increase in individual or cumulative occupational radiation exposure. As such, operation of PVNGS Units 1, 2, and 3 in accordance with the proposed amendment does not involve an unreviewed environmental safety question.
G. MARKED-U TECH C L S EC C 0 G S
~UIT 1 ~Uij 3 3/4 5-5 3/4 5-5 3/4 5-5 B 3/4 5-2 B 3/4 5-2 B 3/4 5-2 B 3/4 5-3 B 3/4 5-3 B 3/4 5-3 d
The following inserts are provided to be incorporated as delineated in the attached marked-up Technical Specification pages:
~INS RTT, Verifying that when a representative sample of 3.5 a 0.005 grams of anhydrous TSP (corrected for moisture content) from a TSP storage basket is submerged, without agitation, in 1.0 2 0.005 liter of 2.5 wt% boric acid solution (nominally 4400 Page 6 of 7
ppm boron) at 135 a 9'F, the pH of the solution as measured at 77 a 9'F is raised to greater than or equal to 7 within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.
Anhydrous TSP is stored in baskets in containment that allow the TSP to dissolve into containment sump water following a large break LOCA. Once dissolved in the containment sump water, the TSP will increase the water pH to greater than or equal to 7. Maintaining the pH at greater than or equal to 7 prevents a significant fraction of dissolved iodine from converting to a volatile form and minimizes the potential of stress corrosion cracking of austenitic stainless steel components in containment following a LOCA.
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