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Category:OPERATING LICENSES-APPLIATION TO AMEND-RENEW EXISTING
MONTHYEARL-99-033, Application for Amends to Licenses NPF-2 & NPF-8,to Change TS Re Control Room,Penetration Room & Containment Purge Filtration Sys & Radiation Monitoring Instrumentation,Which Reflect Agreements Reached in 990909 & 16 Discussions1999-10-0404 October 1999 Application for Amends to Licenses NPF-2 & NPF-8,to Change TS Re Control Room,Penetration Room & Containment Purge Filtration Sys & Radiation Monitoring Instrumentation,Which Reflect Agreements Reached in 990909 & 16 Discussions ML20212C5831999-09-15015 September 1999 Application for Amends to Licenses NPF-2 & NPF-8,committing Util to Transfer Certain CTS Requirements Into Util Controlled Documents & Specifying Schedule for Performing New & Revised ITS Surveillances.Revised License Pages,Encl ML20210R5181999-08-12012 August 1999 Revised Page 6 to 990430 LAR to Operate Farley Nuclear Plant,Unit 1,for Cycle 16,based on risk-informed Approach for Evaluation of SG Tube Structural Integrity.Marked Page of Current License,Included L-99-018, Application for Amend to License NPF-2 for Approval to Operate Unit 1,cycle 16 Only,Based on risk-informed Approach for Evaluation of SG Tube Structural Integrity1999-04-30030 April 1999 Application for Amend to License NPF-2 for Approval to Operate Unit 1,cycle 16 Only,Based on risk-informed Approach for Evaluation of SG Tube Structural Integrity L-99-013, Application for Amends to Licenses NPF-2 & NPF-8.Amends Would Increase Dei Limit from 0.15 to 0.3 Uci/Gram IAW 10CFR50.90.Marked-up & Revised Current TS Encl1999-04-0202 April 1999 Application for Amends to Licenses NPF-2 & NPF-8.Amends Would Increase Dei Limit from 0.15 to 0.3 Uci/Gram IAW 10CFR50.90.Marked-up & Revised Current TS Encl ML20155J4391998-11-0606 November 1998 Application for Amends to Licenses NPF-2 & NPF-8,requesting Change to TS Nuclear Instrumentation Sys Power Range Daily Surveillance Requirement ML20154K2451998-10-12012 October 1998 Application for Amends to Licenses NPF-2 & NPF-8,revising Section 6 of TS by Recognizing Addl Mgt Positions Associated with SG Replacement Project & Providing Ability to Approve Procedures Re Project Which May Affect Nuclear Safety ML20216F7051998-03-12012 March 1998 Application for Amends to Licenses NPF-2 & NPF-8 to Revise Existing TS in Entirety.Amend Consists Primarily of Conversion of Current TS to Improved Ts,Per NUREG-1431,rev 1.Vols 1-10 Contain Listed Attachments ML20198H3561998-01-0707 January 1998 Application for Amends to Licenses NPF-2 & NPF-8,adding Note to TS to Specifically Indicate Normal or Emergency Power Supply May Be Inoperable in Modes 5 or 6 Provided That Requirements of TS 3.8.1.2 Are Satisified ML20198E6531997-12-31031 December 1997 Application for Amends to Licenses NPF-2 & NPF-8,changing Nis IR Neutron Flux Reactor Trip Setpoint & Allowable Value to Be Consistent W/W Std TS,NUREG-1431,Rev 1.Proprietary Safety Analysis,Encl.Proprietary Info Withheld ML20198E2891997-12-30030 December 1997 Application for Amends to Licenses NPF-2 & NPF-8,changing Requirements for Auxiliary Bldg & Svc Water Bldg Batteries, Per NRC Staff Concerns as Described in URI 50-348/97-201 & 50-364/97-201 & NOV 50-348/97-11 & 50-364/97-11 ML20211P5811997-10-16016 October 1997 Application for Amends to Licenses NPF-2 & NPF-8,revising Number of Allowable Charging Pumps Capable of Injecting in RCS When Temperature of One or More of RCS Cold Leg Temperatures Is Less than 180 F ML20211A6811997-09-17017 September 1997 Application for Amends to Licenses NPF-2 & NPF-8,amending Primary Coolant Specific Activity,Per GL 95-05 ML20216C9231997-09-0303 September 1997 Application for Amend to License NPF-2,allowing Reduction in Available Paths to Min of 50% w/3 Per Core Quadrant. Non-proprietary & Proprietary W Repts CAA-97-234 & CAA-97-235,encl.Proprietary Info,Withheld ML20149K0971997-07-23023 July 1997 Application for Amends to Licenses NPF-2 & NPF-8,relocating RCS P/T Limits from TS to Proposed PT Limits Rept IAW Guidance Provided by GL 96-03, Relocation of P/T Limit Curves & LTOP Protection Sys Limits ML20148R7351997-06-30030 June 1997 Application for Amends to Licenses NPF-2 & NPF-8, Incorporating Requirements Necessary to Change Basis for Prevention of Criticality in Fuel Storage Pool.Change Eliminates Credit for Boraflex as Neutron Absorbing Matl ML20148Q0981997-06-30030 June 1997 Application for Amends to Licenses NPF-2 & NPF-8,revising & Clarifying Requirements for CR Emergency & Penetration Room Filtration Sys & Related Storage Pool Ventilation Sys & Revises Radiation Monitoring Instrumentation Channels ML20148K7421997-06-13013 June 1997 Application for Amends to Licenses NPF-2 & NPF-8,proposing Changes Found in Tech Specs 3/4.9.13, Storage Pool Ventilation (Fuel Movement) ML20140A3861997-05-28028 May 1997 Application for Amends to Licenses NPF-2 & NPF-8,clarifying That Testing of Each Shared EDG to Comply W/Sr 4.8.1.1.2.e Is Only Required Once Per Five Years on a Per EDG Basis,Not on Per Unit Basis ML20148E5851997-05-27027 May 1997 Application for Amends to Licenses NPF-2 & NPF-8,revising Applicable Modes for Source Range Nuclear Instrumentation & Providing Allowances for an Exception to Requirements for State of Power Supplies for RHR Discharge to Pump Valves ML20138B9161997-04-23023 April 1997 Application for Amends to Licenses NPF-2 & NPF-8,revising Proposed TS Pages to Include Footnote Concerning Filter Pressure Drop Testing & Mechanical Heater Testing ML20137H6011997-03-25025 March 1997 Application for Amend to License NPF-2,requesting Implementation of voltage-based Alternate Repair Criteria, Per GL 95-05 ML20136F8141997-03-0707 March 1997 Application for Amends to Licenses NPF-2 & NPF-8,revising TS 3/4.6.3 Re Containment Isolation Valves Surveillance Requirements ML20135C6511997-02-24024 February 1997 Application for Amends to Licenses NPF-2 & NPF-8,requesting Revision & Clarification to Surveillance Requirements for Control Room Emergency Filtration Sys,Penetration Room Filtration Sys & Containment Purge Exhaust Filter ML20135C8311997-02-14014 February 1997 Application for Amends to Licenses NPF-2 & NPF-8,revising Specified Max Power Level & Definition of Rated Thermal Power ML20138G9451996-12-26026 December 1996 Application for Amends to Licenses NPF-2 & NPF-8,reflecting Guidance in GL 95-05, SG Tube Support Plate Voltage-Based Repair..., to Use Revised Accident Leakage Limit of 20 Gpm & Include 50% of Rpc Ndds in Calculation.W/O Unit 2 TSs ML20134K5501996-11-15015 November 1996 Application for Amends to Licenses NPF-2 & NPF-8,requesting Deletion of TS 3.6.2.2 Re Containment Spray Additive Sys ML20128F8681996-09-30030 September 1996 Application for Amends to Licenses NPF-2 & NPF-8,relocating cycle-specific Core Operating Parameter Limits to Colr. Proposed Changes Based on Guidance Found in NRC GL 88-16, WOG-90-016,NUREG-1431 & VEGP COLR Approved by NRC ML20117G2911996-08-30030 August 1996 Application for Amend to License NPF-8,requesting Deletion of References to Cycle Specific L* Criteria ML20117D2201996-08-23023 August 1996 Application for Amends to Licenses NPF-2 & NPF-8,requesting to Allow Use of Elevated Sleeve ML20113B6931996-06-24024 June 1996 Application for Amends to Licenses NPF-2 & NPF-8,deleting Requirement for Surveillance of Manual SI Input to Reactor Trip Circuitry Until Next Unit Shutdown ML20113A7991996-06-20020 June 1996 Application to Revise Ts,Reflecting Implementation of 10CFR50,App J,Option B & Represent Crossed Beneficial Licensee Actions ML20112G9711996-06-12012 June 1996 Application for Amends to Licenses NPF-2 & NPF-8,providing Improved Operating Margins as Well as Increased Flexibility W/Respect to Core Designs & Plant Operating Strategy. Rev 2 to NSD-NT-OPL-96-152 Withheld ML20107J9551996-04-23023 April 1996 Application for Amend to License NPF-8,requesting Unit 2 Cycle 11 TS Change for SG Tubes Remaining in Svc ML20107J1521996-04-22022 April 1996 Application for Amend to License NPF-8,reflecting Implementation of New F* Criteria Based on Maintaining Existing Safety Margins for SG Tube Structural Integrity Concurrent W/Allowance for NDE Eddy Current Uncertainty ML20101L9041996-03-29029 March 1996 Application for Amend to License NPF-8,revising TS 3/4.4.6, Steam Generators & Associated Bases,Reflecting Guidance in GL 95-05.Responses to GL & Revised TS Encl ML20095L0161995-12-19019 December 1995 Application for Amends to Licenses NPF-2 & NPF-8,revising Tech Specs Section 3/.7.7 Re Control Room Emergency Ventilation Sys ML20098B0911995-09-26026 September 1995 Application for Amends to Licenses NPF-2 & NPF-8,changing TS 4.6.1.3 to Incorporate Improvements to Containment Air Lock Testing Ref in Chapter 3.6,containment Sys of NUREG-1431, Sts,Westinghouse Plants ML20092F3821995-09-15015 September 1995 Application for Amend to License NPF-2 & NPF-8,eliminating Periodic Pressure Sensor Response Time Testing Requirements ML20084P4901995-05-31031 May 1995 Application for Amends to Licenses NPF-2 & NPF-8,revising TS Associated W/Steam Generator Tube Support Plate voltage- Based Repair Criteria ML20080R8201995-03-0606 March 1995 Application for Amends to Licenses NPF-2 & NPF-8,relocating Seismic & Meteorological Monitoring Instrumentation TSs to FSAR ML20078P8331995-02-14014 February 1995 Application for Amend to Licenses NPF-2 & NPF-8 Re Permanent voltage-based Repair Criteria for Outside Diameter Stress Corrosion Cracking at SG Tube Support Plates for Both Units at Plant ML20077R4071995-01-0909 January 1995 Application for Amends to Licenses NPF-2 & NPF-8, Incorporating line-item TS Improvements to Reduce Surveillance Requirements for Testing During Power Operation in Response to GL 93-05 ML20078S7531994-12-19019 December 1994 Application for Amends to Licenses NPF-2 & NPF-8,revising TS Pages for Mssv,Per NRC Information Notice 94-060, Potential Overpressurization of Main Steam Sys ML20077E3461994-12-0707 December 1994 Application for Amends to Licenses NPF-2 & NPF-8,revising TS to Reflect Guidance in Draft GL 94-XX, Voltage-Based Repair Criteria for Repair of Westinghouse SG Tubes Affected by Outside Diameter Stress Corrosion Cracking ML20078B5451994-10-20020 October 1994 Application for Amends to Licenses NPF-2 & NPF-8,proposing TS 3/4.3.3.6 & Associated Bases,Which Will Delete Requirements for Chlorine Detection Sys from Units 1 & 2 TS ML20072F3401994-08-17017 August 1994 Application for Amends to Licenses NPF-2 & NPF-8,eliminating Periodic Pressure Sensor Response Time Testing Requirements. Rev 1 to WCAP-13787 & Proprietary Rev 1 to WCAP-13632, Elimination of Pressure... encl.WCAP-13632,Rev 1 Withheld ML20070A1001994-06-17017 June 1994 Application for Amend to License NPF-2,revising TS 3/4.2.3 to Increase Nuclear Enthalpy Rise Hot Channel Factor Limit from 1.65 to 1.70 for Vantage 5 Fuel,In Order to Provide Greater Flexibility in Farley Unit 1 Core Design ML20069K2781994-06-10010 June 1994 Application for Amends to Licenses NPF-2 & NPF-8,changing RTS & ESFAS Setpoints Associated W/Sg Water Level. Westinghouse Nonproprietary & Proprietary Version of Rept, SG Lower Level Tap... Encl.Proprietary Rept Withheld ML20064C2111994-02-23023 February 1994 Application for Amend to License NPF-2,revising TS, to Allow Implementation of 2 Volt Interim Plugging Criteria 1999-09-15
[Table view] Category:TEXT-LICENSE APPLICATIONS & PERMITS
MONTHYEARL-99-033, Application for Amends to Licenses NPF-2 & NPF-8,to Change TS Re Control Room,Penetration Room & Containment Purge Filtration Sys & Radiation Monitoring Instrumentation,Which Reflect Agreements Reached in 990909 & 16 Discussions1999-10-0404 October 1999 Application for Amends to Licenses NPF-2 & NPF-8,to Change TS Re Control Room,Penetration Room & Containment Purge Filtration Sys & Radiation Monitoring Instrumentation,Which Reflect Agreements Reached in 990909 & 16 Discussions ML20212C5831999-09-15015 September 1999 Application for Amends to Licenses NPF-2 & NPF-8,committing Util to Transfer Certain CTS Requirements Into Util Controlled Documents & Specifying Schedule for Performing New & Revised ITS Surveillances.Revised License Pages,Encl ML20210R5181999-08-12012 August 1999 Revised Page 6 to 990430 LAR to Operate Farley Nuclear Plant,Unit 1,for Cycle 16,based on risk-informed Approach for Evaluation of SG Tube Structural Integrity.Marked Page of Current License,Included L-99-018, Application for Amend to License NPF-2 for Approval to Operate Unit 1,cycle 16 Only,Based on risk-informed Approach for Evaluation of SG Tube Structural Integrity1999-04-30030 April 1999 Application for Amend to License NPF-2 for Approval to Operate Unit 1,cycle 16 Only,Based on risk-informed Approach for Evaluation of SG Tube Structural Integrity L-99-013, Application for Amends to Licenses NPF-2 & NPF-8.Amends Would Increase Dei Limit from 0.15 to 0.3 Uci/Gram IAW 10CFR50.90.Marked-up & Revised Current TS Encl1999-04-0202 April 1999 Application for Amends to Licenses NPF-2 & NPF-8.Amends Would Increase Dei Limit from 0.15 to 0.3 Uci/Gram IAW 10CFR50.90.Marked-up & Revised Current TS Encl ML20155J4391998-11-0606 November 1998 Application for Amends to Licenses NPF-2 & NPF-8,requesting Change to TS Nuclear Instrumentation Sys Power Range Daily Surveillance Requirement ML20154K2451998-10-12012 October 1998 Application for Amends to Licenses NPF-2 & NPF-8,revising Section 6 of TS by Recognizing Addl Mgt Positions Associated with SG Replacement Project & Providing Ability to Approve Procedures Re Project Which May Affect Nuclear Safety ML20216F7051998-03-12012 March 1998 Application for Amends to Licenses NPF-2 & NPF-8 to Revise Existing TS in Entirety.Amend Consists Primarily of Conversion of Current TS to Improved Ts,Per NUREG-1431,rev 1.Vols 1-10 Contain Listed Attachments ML20198H3561998-01-0707 January 1998 Application for Amends to Licenses NPF-2 & NPF-8,adding Note to TS to Specifically Indicate Normal or Emergency Power Supply May Be Inoperable in Modes 5 or 6 Provided That Requirements of TS 3.8.1.2 Are Satisified ML20198E6531997-12-31031 December 1997 Application for Amends to Licenses NPF-2 & NPF-8,changing Nis IR Neutron Flux Reactor Trip Setpoint & Allowable Value to Be Consistent W/W Std TS,NUREG-1431,Rev 1.Proprietary Safety Analysis,Encl.Proprietary Info Withheld ML20198E2891997-12-30030 December 1997 Application for Amends to Licenses NPF-2 & NPF-8,changing Requirements for Auxiliary Bldg & Svc Water Bldg Batteries, Per NRC Staff Concerns as Described in URI 50-348/97-201 & 50-364/97-201 & NOV 50-348/97-11 & 50-364/97-11 ML20198R5181997-10-29029 October 1997 Amends 132 & 124 to Licenses NPF-02 & NPF-08,respectively, Changing TS 3/4.4.9, Specific Activity & Associated Bases to Reduce Limit Associated W/Dose Equivalent iodine-131 ML20211P5811997-10-16016 October 1997 Application for Amends to Licenses NPF-2 & NPF-8,revising Number of Allowable Charging Pumps Capable of Injecting in RCS When Temperature of One or More of RCS Cold Leg Temperatures Is Less than 180 F ML20211A6811997-09-17017 September 1997 Application for Amends to Licenses NPF-2 & NPF-8,amending Primary Coolant Specific Activity,Per GL 95-05 ML20216C9231997-09-0303 September 1997 Application for Amend to License NPF-2,allowing Reduction in Available Paths to Min of 50% w/3 Per Core Quadrant. Non-proprietary & Proprietary W Repts CAA-97-234 & CAA-97-235,encl.Proprietary Info,Withheld ML20149K0971997-07-23023 July 1997 Application for Amends to Licenses NPF-2 & NPF-8,relocating RCS P/T Limits from TS to Proposed PT Limits Rept IAW Guidance Provided by GL 96-03, Relocation of P/T Limit Curves & LTOP Protection Sys Limits ML20148R7351997-06-30030 June 1997 Application for Amends to Licenses NPF-2 & NPF-8, Incorporating Requirements Necessary to Change Basis for Prevention of Criticality in Fuel Storage Pool.Change Eliminates Credit for Boraflex as Neutron Absorbing Matl ML20148Q0981997-06-30030 June 1997 Application for Amends to Licenses NPF-2 & NPF-8,revising & Clarifying Requirements for CR Emergency & Penetration Room Filtration Sys & Related Storage Pool Ventilation Sys & Revises Radiation Monitoring Instrumentation Channels ML20148K7421997-06-13013 June 1997 Application for Amends to Licenses NPF-2 & NPF-8,proposing Changes Found in Tech Specs 3/4.9.13, Storage Pool Ventilation (Fuel Movement) ML20140A3861997-05-28028 May 1997 Application for Amends to Licenses NPF-2 & NPF-8,clarifying That Testing of Each Shared EDG to Comply W/Sr 4.8.1.1.2.e Is Only Required Once Per Five Years on a Per EDG Basis,Not on Per Unit Basis ML20148E5851997-05-27027 May 1997 Application for Amends to Licenses NPF-2 & NPF-8,revising Applicable Modes for Source Range Nuclear Instrumentation & Providing Allowances for an Exception to Requirements for State of Power Supplies for RHR Discharge to Pump Valves ML20138B9161997-04-23023 April 1997 Application for Amends to Licenses NPF-2 & NPF-8,revising Proposed TS Pages to Include Footnote Concerning Filter Pressure Drop Testing & Mechanical Heater Testing ML20137H6011997-03-25025 March 1997 Application for Amend to License NPF-2,requesting Implementation of voltage-based Alternate Repair Criteria, Per GL 95-05 ML20137E2891997-03-24024 March 1997 Amends 125 & 119 to Licenses NPF-2 & NPF-8,respectively, Revising TS to Incorporate Latest Revised Topical Repts Governing Installation of Laser Welded SG Tube Sleeves ML20136F8141997-03-0707 March 1997 Application for Amends to Licenses NPF-2 & NPF-8,revising TS 3/4.6.3 Re Containment Isolation Valves Surveillance Requirements ML20135C6511997-02-24024 February 1997 Application for Amends to Licenses NPF-2 & NPF-8,requesting Revision & Clarification to Surveillance Requirements for Control Room Emergency Filtration Sys,Penetration Room Filtration Sys & Containment Purge Exhaust Filter ML20135C8311997-02-14014 February 1997 Application for Amends to Licenses NPF-2 & NPF-8,revising Specified Max Power Level & Definition of Rated Thermal Power ML20138G9451996-12-26026 December 1996 Application for Amends to Licenses NPF-2 & NPF-8,reflecting Guidance in GL 95-05, SG Tube Support Plate Voltage-Based Repair..., to Use Revised Accident Leakage Limit of 20 Gpm & Include 50% of Rpc Ndds in Calculation.W/O Unit 2 TSs ML20134K5501996-11-15015 November 1996 Application for Amends to Licenses NPF-2 & NPF-8,requesting Deletion of TS 3.6.2.2 Re Containment Spray Additive Sys ML20128F8681996-09-30030 September 1996 Application for Amends to Licenses NPF-2 & NPF-8,relocating cycle-specific Core Operating Parameter Limits to Colr. Proposed Changes Based on Guidance Found in NRC GL 88-16, WOG-90-016,NUREG-1431 & VEGP COLR Approved by NRC ML20117G2911996-08-30030 August 1996 Application for Amend to License NPF-8,requesting Deletion of References to Cycle Specific L* Criteria ML20117D2201996-08-23023 August 1996 Application for Amends to Licenses NPF-2 & NPF-8,requesting to Allow Use of Elevated Sleeve ML20113B6931996-06-24024 June 1996 Application for Amends to Licenses NPF-2 & NPF-8,deleting Requirement for Surveillance of Manual SI Input to Reactor Trip Circuitry Until Next Unit Shutdown ML20113A7991996-06-20020 June 1996 Application to Revise Ts,Reflecting Implementation of 10CFR50,App J,Option B & Represent Crossed Beneficial Licensee Actions ML20112G9711996-06-12012 June 1996 Application for Amends to Licenses NPF-2 & NPF-8,providing Improved Operating Margins as Well as Increased Flexibility W/Respect to Core Designs & Plant Operating Strategy. Rev 2 to NSD-NT-OPL-96-152 Withheld ML20107J9551996-04-23023 April 1996 Application for Amend to License NPF-8,requesting Unit 2 Cycle 11 TS Change for SG Tubes Remaining in Svc ML20107J1521996-04-22022 April 1996 Application for Amend to License NPF-8,reflecting Implementation of New F* Criteria Based on Maintaining Existing Safety Margins for SG Tube Structural Integrity Concurrent W/Allowance for NDE Eddy Current Uncertainty ML20101L9041996-03-29029 March 1996 Application for Amend to License NPF-8,revising TS 3/4.4.6, Steam Generators & Associated Bases,Reflecting Guidance in GL 95-05.Responses to GL & Revised TS Encl ML20095L0161995-12-19019 December 1995 Application for Amends to Licenses NPF-2 & NPF-8,revising Tech Specs Section 3/.7.7 Re Control Room Emergency Ventilation Sys ML20098B0911995-09-26026 September 1995 Application for Amends to Licenses NPF-2 & NPF-8,changing TS 4.6.1.3 to Incorporate Improvements to Containment Air Lock Testing Ref in Chapter 3.6,containment Sys of NUREG-1431, Sts,Westinghouse Plants ML20092F3821995-09-15015 September 1995 Application for Amend to License NPF-2 & NPF-8,eliminating Periodic Pressure Sensor Response Time Testing Requirements ML20084P4901995-05-31031 May 1995 Application for Amends to Licenses NPF-2 & NPF-8,revising TS Associated W/Steam Generator Tube Support Plate voltage- Based Repair Criteria ML20080R8201995-03-0606 March 1995 Application for Amends to Licenses NPF-2 & NPF-8,relocating Seismic & Meteorological Monitoring Instrumentation TSs to FSAR ML20078P8331995-02-14014 February 1995 Application for Amend to Licenses NPF-2 & NPF-8 Re Permanent voltage-based Repair Criteria for Outside Diameter Stress Corrosion Cracking at SG Tube Support Plates for Both Units at Plant ML20077R4071995-01-0909 January 1995 Application for Amends to Licenses NPF-2 & NPF-8, Incorporating line-item TS Improvements to Reduce Surveillance Requirements for Testing During Power Operation in Response to GL 93-05 ML20078S7531994-12-19019 December 1994 Application for Amends to Licenses NPF-2 & NPF-8,revising TS Pages for Mssv,Per NRC Information Notice 94-060, Potential Overpressurization of Main Steam Sys ML20077E3461994-12-0707 December 1994 Application for Amends to Licenses NPF-2 & NPF-8,revising TS to Reflect Guidance in Draft GL 94-XX, Voltage-Based Repair Criteria for Repair of Westinghouse SG Tubes Affected by Outside Diameter Stress Corrosion Cracking ML20078B5451994-10-20020 October 1994 Application for Amends to Licenses NPF-2 & NPF-8,proposing TS 3/4.3.3.6 & Associated Bases,Which Will Delete Requirements for Chlorine Detection Sys from Units 1 & 2 TS ML20072F3401994-08-17017 August 1994 Application for Amends to Licenses NPF-2 & NPF-8,eliminating Periodic Pressure Sensor Response Time Testing Requirements. Rev 1 to WCAP-13787 & Proprietary Rev 1 to WCAP-13632, Elimination of Pressure... encl.WCAP-13632,Rev 1 Withheld ML20070A1001994-06-17017 June 1994 Application for Amend to License NPF-2,revising TS 3/4.2.3 to Increase Nuclear Enthalpy Rise Hot Channel Factor Limit from 1.65 to 1.70 for Vantage 5 Fuel,In Order to Provide Greater Flexibility in Farley Unit 1 Core Design 1999-09-15
[Table view] |
Text
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Dave Moray Southtrn Nuclear E 5
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^pril 2.1999 SOUTHERN k L COMPANY
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Drop to Wriv hur GM Docket Nos.: 50-348 _ NEL-99-0131 "5E364 1 e
U. S. Nuclear Regulatory Commission !
ATTN: Document Control Desk -
Washington, D. C. 20555-0001 Joseph M. Failey Nuclear Plant Reactor Coolant Svstgmjpecific Activity Technical Specifications Change Recmesi Ladies and Gentlemen:
!!y NRC letter dated October 29,1997, Amendment Nos.132 and 124 were issued for Farley Nuclear Plant Units I and 2, respectively. These amendments reduced the dose equivalent iodine (DEI) limits from 0.3 pCune/ gram to 0.15 pCurie/ gram. That adjustment in the DEI limit was needed due to the calculated steam line break (SLB) steam generator tube leakage being in excess of tlE leak rate assumption imposed as a result of using steam generator alternate repair criteria (ARC). The increased tube leakage was calculated using the results of Unit I test data from the spring 1997 outage and adjusting for temperature considerations. Additional detail may be found in the Southern Nuclear Operating Company (SNC) transmittal letter (Woodard to NRC) for the DEI amendment request dated September 17,1997. The projected EOC leakage in the event of a steamline break is significantly less than the current 23.8 gpm limit. Consequently, margin exists ,
that would allow raising the DEI limits. Therefore, SNC is submitting this amendment request to increase the DEI limit from 0.15 to 0.3 pCurie/ gram in accordance with 10 CFR 50 90.
Enclosure i provides the basis of the proposed Technical Specifications change. Enclosure 2 provides the required significant hazards evaluation, wherein SNC detennined that the proposed change does not invoive a significant hazards consideration as dermed by 10 CFR 50.92. Enclosure 3 provides the revised Current Technical Specification pages. Enclosure 4 provides the revised improved Technical Specification pages.
SNC has performed an assessment of the impact of the proposed revision to the Technical Specifications on the environment and has determined that there is no impact on the environment.
The proposed revision does not affect the types of any radiological or non-radiological ellluents that may be released ofTsite. Plant releases during nonnal operation may increase slightly. Ilowever, releases will continue to be maintained within regulatory limits. In addition, ofTsite dose from accident conditions also will remain within regulatory limits. No significant increase in individual or cumulative occupational radiation exposures will result from this revision. Finally, the revision does not involve the use of any resources not previously considered in the Final Environmental Statement related to the operation of Farley Nuclear Plant.
9904070393 990402 POR W '
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Page 2 U. S. Nuclear Regulatory Conunission
. A copy of these proposed changes is being sent to Dr. D. E. Williamson, the Alabama State
~ Designee, in accordance with 10 CFR 50 91(b)(l)
Unit i DEI has increased due to fuel pin leakage. Since additional fuel leakage could cause the current DEI limit to be exceeded later in this cycle, approval of this Technical Specification change is requested on an expedited basis. For consistency, the Unit 2 limit is proposed to be changed to match Unit I The current calculated projected end of cycle SLil steam generator tube leakage value -
has sufficient margin to accept this proposed change. The DEI limits will change to 0.5 pCurie/ gram upon implementation of the Tecimical Specifications amendment request associated with the upcoming steam generators replacements. If you have any questions, please advise.
'l Respectfully submitted, ]
SOUTilERN NUCLEAR OPERATING COMPANY i
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Dave Morey b to and subscribed before me Il 's _A. day of _k Nlt 999 f
d /H4&?Of W L Notary'Public/ /
My Commission Expires: HY COMMtS$10N EXP!RES M.E 10. 2Xe EWC/maf:1-SDEl. DOC
Enclosures:
- 1. - Basis for Proposed Technical Specifications Change !
- 2. Significant IIazards Evaluation j
- 3. Current Technical Specifications Pages
- 4. Improved Technical Specifications Pages L
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.U. S1 Nuclear Regulatory Commission j 1
cc Southern Nuclear Operatinn Compaiiv Mr. L: M. Stinson, General Manager - Farley i U - S. Nuclear Reculatory Commission: Washincton. D C.
Mr.1; 1.; Zinunerman, Licensing Project Manager - Farley U. S.' Nuclear Regulatory Commission. Recion 11.
Mr. L. A. Reyes, Regional Administrator -
Mr. T. P. Johnson, Senior Resident inspector - Farley 1
Alabama Department of Public Health j
. Dr. D. E Williamson, State Health Omccr i I
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. Enclosure 1 Farley Nuclear Plant Reactor Coolant System Specific Activity Limit Basis for Proposed Technical Specifications Change l
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Farley Nuclear Plant Reactor Coolant System Specific Activity Limit Basis for Proposed Technical Specifications Change l l
Introduction l Implementation of the voltage-based repair criteria for Westinghouse steam generators affected by outside diameter stress corrosion cracking requires the implementation of a primary-to-secondary leakage limit in i the event of a steam line break outside containment. By limiting the primary-to-secondary leakage, the radiological consequences of a postulated accident will not exceed the guideline values of 10 CFR 100.
He quantity of primary-to-secondary leakage that is acceptable in the event of a postulated accident is dependent on the allowable activity in the primary coolant. )
Description of the Amendment Reauest ,
l The proposed amendment will modify Technical Specification 3/4.4.9, " Specific Activity," and the '
associated Bases to increase the limit associated with dose equivalent iodine-131. The steady-state dose equivalent iodine-131 limit will increase to 0.3 pCuric/ gram. The transient limit for 80% to 100% power ;
provided by Technical Specification Figure 3.4-1 will increase to 18 pCurie/ gram with a corresponding l increase in the 0% to 80% power limits.
l Basis By letter dated June 4,1992, Southern Nuclear submitted an assessment of the radiological dose consequences of a main steam line break. That calculation, based on a dose equivalent iodine-131 limit of 1.0 Curie / gram for steady-state with a corresponding transient limit, concluded that the leak rate in the faulted steam generator should be limited to 5.7 gpm.
By letter dated April 5,1994, the NRC Staffissued Amendment No.106 to the Farley Unit 1 Technical Specifications. His amendment reduced the dose equivalent iodine-131 limit to 0.25 Curie / gram for steady-state with a corresponding reduction in the transient limit. This change resulted in a leakage limit of 4 x 5.7 gpm or 22.8 gpm.
I By letter dated September 28,1995, the NRC Staffissued Amendment No. I17 for the Farley Unit 1 Technical Specifications. This amendment increased the dose equivalent iodine-131 limit to 0.5 Curie / gram for steady-state with a corresponding increase in the transient limit. This change resulted in a leakage limit of 2 x 5.7 gpm or 11.4 gpm. The NRC Safety Evaluation included a description of ,
confirmatory calculations performed by the NRC Staff that " concluded that a leak rate of 11.4 gpm is an acceptable limit of the maxunum primary to secondary leakage initiated by the steam line break accident."
By letter dated May 19,1997, the NRC Staffissued Amendment No.128 for the Farley Unit 1 Tecimical Specifications. His amendment reduced the dose equivalent iodine-131 limit to 0.3 Curie / gram for steady-state with a corresponding decrease in the transient limit. His change resulted in a leakage limit of 3.333 x 5.7 gpm or 19 gpm. Subsequent to this amendment, it was discovered that the steam line break leakage limit and steam line break leakage projections had not consistently accounted for the density of water at various temperatures. This finding resulted in a reduction of the steam line break leakage limit to I a value that is 71% of the 19 gpm value calculated above, or 13.5 gpm.
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9 Enclosure i . _ _
Page 2 Basis for Proposed Technical Specification Change Reduction in Dose Equivalent Iodine-131 Limits -
By letter dated October 29,1997, the NRC Staffissued Amendment No.132 for the Farley Unit i Technical Specifications. This amendment reduced the dose equivalent iodine-131 limit to 0.15 Curie / gram for steady-state with a corresponding reduction in the transient limit of 9 Curie / gram.. This change resulted in a leakage limit of 23.8 gpm.
Similar Technical' Specifications changes have been approved for Farley Unit 2.
Unit i DO his increased due to fuel pin leakage, requiring recovery of operating margin for DEI. For .
mancnm rae Unit 2 DEI limit is being changed to match Unit 1. 'Ihe current projected end of cycle SLB ,
wakAp is 8.2 gpm for Unit I and 2.0 gpm for Unit 2. These values are well below the limit of 23.8 gpm and demonstrate that existing margin can be recovered without impacting offsite dose analysis. 'This proposed change will increase DEI to a value of 0.3 Curie / gram and reduce the ARC SG SLB leakage limit to 11.8 gpm. Calculated offsite dose will remain within regulatory limits at 29.56 Rem at the low
_ population zone boundary as a result of this proposed change. The DEI limits will change to 0.5 pCurie/ gram upon implementation of the Technical Specifications amendment request associated with the upcoming steam generators replacements.
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. Enclosure 2 Faricy Nuclear Plant Reactor Coolant System Specific Activity thnit Technical Specifications Change Significant Hazards Evaluation i
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Farley Nuclear Plant Reactor Coolant System Specific Activity Limit
. Technical Specifications Change Significant flazards Evaluation Introduction
' Implementation of the voltage-based repair criteria for Westinghouse steam generators affected by outside diameter stress corrosion cracking requires the implementation of a primary-to-secondary leakage limit in the event of a steam line break outside containment. . By limiting the primary-to-secondary leakage, the radiological consequences of a postulated ' accident will not exceed the guideline value of 10 CFR 100.
The quantity of primary-to-secondary leakage that is acceptable in the event of a postuinted accident is dependent on the allowable activity in the primary coolant.
- i Description of the Amendment Reauest l il
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~ As required _by 10 CFR 50.91(a)(1), this analysis is provided to demonstrate that a proposed amendment to increase the dose equivalent iodine limits for Farley Units I and 2 represents no significant hazards. In ~ !
accordance with 10_CFR 50.92(c), implementation of the proposed license amendment was analyzed using the following standards and found not to: 1) involve a significant increase in the probability or consequences for an accident previously evaluated; 2) create the possibility of a new or different kind of j accident from any accident previously evaluated; or 3) involve a significant reduction in a margin of safety. ,
- He proposed amendment will modify Technical Specification 3/4.4.9, " Specific Activity," and the l associated Bases to increase the limit associated with dose equivalent iodine-131. The steady-state dose .
equivalent iodine-131 limit will be increased to 0.3 Curie / gram. The transient limit for 80% to 100%
power provided by Technical Specification Figure 3.4 1 will be increased to 18 Curie / gram. Forless than 80% power, the transient limits will be increased by 9 Curic/ gram for each power level. This change will result in a density compensated leakage limit of i 1.8 gpm for the affected SG. Both units end of cycle MSLB event estimated leakage rate is below this limit.. The calculation of these limits is consistent with that submitted originally by Southem Nuclear Operating Company letter dated June 4,1992 and subsequently discussed in safety evaluations issued by the NRC Staffin letters dated April 5,1994, September 28,1995, May 19,1997, and October 29,1997.
He following evaluation applies to the Improved Technical Specifications (ITS) submittal as wHl as Current Technical Specifications. In addition to the changes associated with the DEI change some editorial j
. changes have been made to the ITS pages.
Evaluation i ne proposed Technical Specifications change will result in a dose equivalent iodine-131 limit of 0.3
- Curie / gram for steady-state and a corresponding increase in the transient limit. The transient limit will be 18 Curie / gram above 80% power with limits as shown on Figure 3.4 1 below 80% power.
Analysis Conformance of the proposed amendment to the standards for detennining that it involves no significant
- hazards as defined in 10 CFR 50.92 is shown by the following.
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=, Enclosure 2 Page 2 j Significant Hazards Evaluation
- Reducti'on in Dose Equivalent Iodine-131 Limits
- l. Operation of Farley Units I and 2 in accordance with the proposed license amendment does not involve a significant increase in the probability or consequences of an accident previously evaluated.
The increase in the dose equivalent iodine limits, both steady-state and transient, will not increase the probability of any accident evaluated since no physical changes to the plant are being 'made. The ;
consequences of any accident previously evaluated will not be significantly increased since the doses remain a small fraction of the regulatory limit.
- 2. The proposed license amendment does not create the possibility of a new or different kind of 4 accident from any accident previously evaluated. -
The increase in the dose equivalent iodine limits, both steady-state and transient, will not create the possibility of a new or different kind of accident from any accident previously evaluated since no physical j changes to the plant are being made. He accidents of concem continue to be those that have previously been analyzed. ,
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- 3. ~ The proposed license amendment does not involve a significant reduction in a margin of safety.
He calculated potential radiological consequences from the main steam line break accident (the bounding event) remain within the regulatory exposure guidelines and have not changed significantly. Increase of the dose equivalent iodine limit along with a corresponding decrease of allowable steam line break pnmary-to- )
secondary steam generator leakage provides a compensating offsite dose effect. Although the calculated dose increases slightly, the dose remains within a small fraction of the regulatory limit (30.0 REM at the LPZ boundary). Consequently, there is no significant reduction in any margin of safety.
Conclusion Based on the preceding analysis, it is concluded that operation of Farley Units I and 2 following the increase in the dose equivalent iodine-131 limits in accordance with the proposed amendment does not involve a significant increase in the probability or consequence of an accident previously evaluated, create the possibility of a new or different kind of accident from any accident previously evaluated, or significantly reduce any margins of safety. Therefore, the license amendment does not involve any i significant hazards as defined in 10 CFR 50.92.
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Enclosure 3 Farley Nuclear Plant Reactor Coolant System Specific Activity Technical Specifications Change Request Current Technical Specification Pages l
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1 Pen and Ink Mark-ups For Current Technical Specifications
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