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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
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.___ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _
e Malling Addr;ss Alanama Power Company
. 600 North 18th Street Post Office Ocx 2641 Dirmingham Alabama 35291 Telephone 205 783-6081 F. L. Clayton, Jr.
Senior Vice Presiaent Fhnttidge Duilding / OkXlIlldPOWCf February 17, 1981 l
Docket Nos. 50-348 50-364 Director, Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission Washington, D.C. 20555 Attention: Mr. S. A. Varga Joseph M. Farley Nuclear Plant - Units 1 and 2 Proposed Technical Specification Change Gentlemen:
Pursuant to the commitments made by Alabama Power Company in the January 20, 1984 meeting with the NRC staff, this letter transmits a revised proposed technical specification change request for the Rod Control System at Farley Nuclear Plant - Units 1 and 2.
Attachment 1 contains a detailed description of the Rod Control System, the proposed technical specification change and justifications for the change. Attachment 2 is the proposed changed technical specification pages.
These proposed changes de not involve a Significant Hazards Consideration as defined in 10CFR50.92. These changes are similar to example (iv) of " Examples of Amendments that are Considered Not Likely to Involve Significant Hazards Considerations" listed in 48FR14870 dated April 6, 1983. These proposed changes are similar in that these changes request relief from an operational restriction which can now be lifted based
! upon previous NRC staff review.
The Plant Operations Review Committee has reviewed this proposed change. The Nuclear Operations Review Board will review this proposed change at a future meeting. Westinghouse Corporation has reviewed and concurred with the intent of this change.
y}lG- Y B402220511 840217 0 0\ '
- 90/457 PDR ADOCK 05000348 P PDR S
Mr. S. A. Varga February 17, 1984 U. S. Nuclear Regulatory Comission Page 2 This proposed technical specification change is considered to be a Class III Amendment for Unit 1 and Class I Amendment for Unit 2 pursuant to 10CFR170.22. Since the previous request (March 4, 1983) was denied, a check for this revised change request in the amount of $4,400.00 is enclosed.
Pursuant to 10CFR50.90 three (3) signed originals and 40 conforming copies of this proposed change are enclosed. Pursuant to 10CFR50.91 (b) we have provided a copy of this letter and its attachments to Dr. I. L. Myers the designated representative of the State of Alabama.
If you have any questions, please advise.
Yours truly, F. . Clayton, r.
' FLCJr/CJS:grs-D2 SWORN TO AND SUBSCRIBED BEFORE ME Attachments cc: Mr. R. A. Thomas THIS lb DAY OF d M V1984 Mr. G. F. Trowbridge -
C Mr. J. P. O'Reilly f OJ Notary Public Mr. E. A. Reeves Mr. W. H. Bradford Dr. I. L. Myers My Comission Expires: 1-1687 l
bc: Mr. W. O. Whitt Mr. R. P. Mcdonald Mr. H. O. Thrash
, M r. O. D. . ngsley, J r.
Mr. W. G. Hairston, III Mr. J. W. McGowan Mr. C. D. Nesbitt Mr. R. G. Berryhill Mr. D. E. Mansfield Mr. J. A. Ripple Mr. W. G. Ware Mr. L. B. Long Mr. B. J. George Mr. J. R. Crane Mr. K. C. Gandhi Reference Listing i
Attachment 1 Description of the Proposed Change to the Rod Control System Technical Specification I. Background Information By letters dated March 4 and July 8,1983 Alabama Power Company requested a change to Technical Specification 3/4.1.3. The purpose of this change was to permit adequate time for the diagnosis and repair of electrical problems in the Rod Control System (non-safety related) before a shutdown would be required. By letter dated September 21, 1983 the NRC denied Alabama Power Company's request.
On January 20, 1984 Alabama Power Company held a meeting with the NRC in Bethesda, Maryland to provide in-depth information on the Rod Control System and how symptoms and diagnostic procedures can provide the plant operators with the ability to discriminate between Rod Control System electrical malfunctions (which are not safety significant) and mechanical binding of the control rods. Pursuant to the NRC request in the meeting, Alabama Power Company is formally submitting the material provided to the NRC Staff at the meeting. In addition, Alabama Power Company has revised tne proposed technical specification request of March 4, 1983 to be consistent with the meeting conclusions.
II. Proposed Technical Specification Change It is proposed that Technical Specification 3.1.3.1 be revised to permit 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> for the performance of diagnostic procedures to determine the source of inoperability of the control rod (s) due to
- electrical problems and repair of the Rod Control System prior to orderly shutdown.
III. Justification for th. Proposed Change A. Rod Control System Description
- 1) Arrangement of Mechanisms The Farley Nuclear Plant is a three loop plant with forty-eight (48) full length rod drive mechanisms arranged into banks and groups. A typical bank and group arrangement is shown in Figure 1. A group consists of four mechanisms that are electrically paralleled to ste A bank of mechanisms consists of two (2)pgroups simultaneously.
that are moved in staggered fashion such that the groups are always within one
_ . . _ ._ _ . _ _ _ _ . _ _ _ _ . . _ . . -- . _-- -_ m _ _ _ _ __._ ._ ._ . - _
i .
Attachment 1 Description of the Proposed Change to the Rod Control System Technical Specification Page 2 step of each other. The arrangement includes two (2) shutdown :
banks, A and B, and four (4) control Banks A, B, C and D.
! Control banks are moved in overlap in the following withdrawal sequence: When Control Bank A reaches a predetermined height in the top half of the core, Control Bank B starts to move out with A. Control Bank A stops at the top of the core and Bank B continues until it reaches a predetermined height in the top half of the core when Control Bank C starts to move out with .
. B. This sequence continues until all rods are withdrawn. The j insertion sequence is the opposite of the withdrawal sequence.
- 2) Main Control Room Controls Controls for the Rod Control System located in the Main Control Room are listed in Figure 2. The In-Hold-Out lever is used for manual rod motion and is located on the Main Control Board.
Also, on the Main Control Board is a Bank Selector Switch with
- eight (8) positions. In the manual position, control banks are moved from the In-Hold-Out leter in overlap. Control banks are moved in overlap by the automatic Tavg control system with the i
switch in the auto position. Six (6) additional positions are provided for individual bank movement.
Step counters, one for each group, are ' located on the Main Control Board to display demanded rod position. A Digital Rod Position Indication System, not connected to the Rod Control System, is used to display actual rod position and is used in codunction with the step counters to determine deviation between demanded and actual position.
In-out 1tghts show the request for rod motion from either the In-Hold-Out lever or the Automatic Tavg Control System. A
, startup pushbutton is provided to reset the step counters and all internal system counters such as the bank overlap counter on startup. An alarm reset pushbutton resets internal system failure detectors and alarms which include a seal-in feature.
1.if t coil disconnect switches, one for each mechanism, are provided to assist in retrieval of a dropped rod.
i Two (2) annunciators are located on the control board: a i Rod Control Urgent Failure and a Rod Control Non-Urgent Failure Al am. The Rod Control Urgent Failure Alarm indicates that a control system failure has occurred that would affect the ability of the control system to move rods. A Rod Control Non-Urgent Failure Alarm indicates failure of one or more redundant power supplies that feed the system printed circuit cards.
e - . ~ --- e. > .n-.- . - , . - .-r,~ ..+.----.---e, -n.,,-vw --y- ,,,n--,, ,. , . _ , ,,.-n --~ nae.--.,,,,,-,. - ~ , . . , , - - , . . , , . ,
Attachment 1 Description of the Proposed Change to the Rod Control System Technical Specification Page 3
- 3) Basic Thyristor Bridge Control Circuit Three (3) thyristors forming a half wave phase controlled bridge supply current to four (4) mechanism coils (either lift, movable, or stationary gripper) as shown in Figure 3. Current feedback signals from shunts in series with each coil are used to regulate the current commanded by a slave cycler located in the system logic cabinet.
- 4) Power Cabinet Power Circuits Five (5) thyristor bridges form one system power cabinet as shown in Figure 4. Four (4) power cabinei.s are used in the system. The power cabinet amplifies low level command signals from a slave cycler in the logic cabinet. One (1) power cabinet drives three (3) groups of four (4) mechanisms and is capable of moving one (1) group while holding the other two (2) in position. The selection as to which group is to move is made with multiplexing thyristors, one (1) for each group of movable coils and one (1) for each lift coil. The lift coil multiplexing thyristors also serve as lift disconnect switches for retrieving a dropped rod.
- 5) System Block Diagram Four (4) power cabinets are supplied with power from two motor generator sets normally operating in parallel through two reactor trip breakers in series as shown in Figure 5. The logic cabinet includes a pulser, master cycler, bank overlap unit, and four (4) slave cyclers. The pulser determines the speed of rod motion (1) as directed by the reactor Tavg control system when automatic operation is selected or (2) by a preset speed when manual operation is selected. The master cycler directs pulses from the pulser alternately to the slave cyclers for the two (2) groups in a bank. Selection of which bank or banks are to move is done by the bank overlap unit. The slave cycler sequences the mechanism coils through one (1) step, either in or out for each "go" pulse from the master cycler. A DC hold cabinet is provided to allow replacement of printed circuit cards in the power ca'oinet while the plant is in operation.
l Attachment 1 Description of the Proposed Change to the Rod Control System Technical Specification Page 4 B. Rod Control System Diagnostic Features
- 1) Failure Detection and Alarms A Rod Control Urgent Failure Alarm is actuated by five (5) failure detectors in each power cabinet or by three (3) failure detectors in the logic cabinet as shown in Figure 6. A Rod Control Urgent Failure Alarm stops automatic rod motion and permits manual movement of a selected bank if the logic cabinet and the two (2) power cabinets associated with the selected bank are not in urgent alarm.
Dewetion of a failure by a failure detector results in the following indications:
- a. A failure detector lamp, one for each type of failure, located on the edge of a printed circuit card in the failed cabinet is energized.
- b. A red urgent failure lamp on the front of the failed cabinet is energized.
- c. A " Rod Control Urgent Failure Alarm" annunciator in the Main Control Room is actuated.
A Rod Control Non-Urgent Failure Alarm indicates failure of one (1) of a number of redundant power supplies and does not effect the operation of the system.
- 2) Effect of Mechanism Mechanical Failure on Control System The Rod Control System operates independently of the rod drive
. mechani sms. Nothing has been included in the system, eitner by design or inadvertantly, to allow it to see movement of the mechanism mechanical parts, the drive shaft or rod control clusters; therefore, mechanical binding would not be detected by or cause a Rod Control System alarm. This has been verified many times during factory checkout of completed systems where the test loads consist only of simulated mechanism coils with iron pipes in the center to approximate the magnetic properties of the coils. Checkout of the Rod Control System at the sites are generally done during Hot Functional Testing with only the mechanism coils connected and no reactor core, rods, or drive shafts in place.
[4
Attachment 1 Description of the Proposed Change to the Rod Control System Technical Specification Page 5
- 3) How to Distinguish Between Control System and Mechanism Problems Based on the previous discussion and Figure 7, a Red Control Urgent Failure Alarm must be the result of a control system failure and cannot be related to a mechanically inoperable rod or rods. There are failures that do not result in a Rod Control Urgent Failure Alann that could prevent one or more rods from moving. In this case, tha problem can be traced to either the control system or mechanism by monitoring the mechanism coil currents. Built-in test points are located in the power cabinet.s for this purpose. If the control system will not vary the currents to the mechanism coils, the problem must be in tile control system and not the mechanisms. If the control system varies currents to the coils, then the mechanism may be suspect. Grossly abnormal currents would indicate control system problems and mildly abnormal currents would indicate mechanism problems. Recordings of the currents would have to be studied in this event. Whatever the cause of the inability to move control rods, repair or shutdown consistent with existing technical specifications would be initiated.
C. Process for Identifying Root Cause of Rod Control System Malfunctions
- 1) Troubleshooting and repair of Rod Control System malfunctions require adequate time to systematically implement diagnostic procedures to identify the malfunction and its root cause as well as repair the system.
Replacement of many, but not all, components in the logic and power cabinets is possible while maintaining all rods in a fixed position; however, determination of which components can be replaced takes a thorough analysis of that component's functions in the system and should not be done hurriedly. The following typical sequence of events should occur for a major rod control problem in which no rods are dropped but a R0D CONTROL URGENT FAILURE ALARM is received:
- a. Initiate planning which results in I&C personnel inspecting cabinets and determining which cabinet has the problem.
Estimated time is 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.
- b. I&C supervisory personnel are notified (back shifts and week-ends), travel to site, and are briefed on initial findings - estimated time 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.
Attachment 1 Description of the Proposed Change to the Rod Control System Technical Specifh:ation Page 6
- c. Procedure for more detailed troubleshooting is implemented. Estimated time is 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
- d. Westinghouse rod control expects are contacted by telephone for additional technical assistance based on results of step c above and anticipatory repair efforts are planned.
Problem is located. Estimated time is 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
- e. Repair parts, if not available on-site, are placed on emergency order and flown to site. Esticated time is 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
- f. Repair is made and system is functionally tested by stepping affected rods. Estimated time is 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.
D. Conclusion The proposed change is considered to increase trie margin of safety.
Thirty-six hours to diagnose and repair electrical problems will prevent hurried, and therefore less safe, diagnosis of malfunctions other than rod misalignment or mechanical binding in the non-safety related Rod Control System. Insufficient time (i.e., 6 hour6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />s-permitted by existing technical specifications) to find the root cause of a malfunction necessitates treating symptoms as opposed to implementing permanent solutions. This change would minimize the potential for dropped or misaligned rods or any further Rod Control System malfunctions as a result of inadequate time for proper diagnostic test procedure performance. The additional time will also permit the operating personnel more flexibility in voluntary investigations of suspected rod control system problems.
The proposed change does not increase the probability or consequences of accidents previously evaluated because control rods will remain trippable thereby maintaining shutdown margin. In addition, the power distribution will continue to be regulated by other existing technical specifications during the proposed 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> allowed for testing and repair of the Rod Control System.
The proposed change does not create the possibility of a new or different kind of accident previously evaluated, rather, it allows sufficient time for licensee personnel to perform orderly maintenance thereby minimizing the potential for human error in the diagncsis and repair of rod control malfunctions. Alabama Power Company and Westinghouse do not feel that the 36 hour4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> period pennitted for troubleshooting and repair constitutes a decrease in plant safety.
- _ - _ _ _ - _ _ _ _ _ _ _ _ - _ _ _ _ _ _ _ 1
FNP SHUTDOWN - GROUP 1 - 4 BANK A
- GROUP 2~-- 4 SHUTDOWN GROUP 1 - 4 BANK B
- GROUP 2 - 4 MECHANISM ARRANGEMENTS CONTROL - GROUP 1- 4 BANK A -
- GROUP 2 - 4
- GROUP 1-CONTROL 4 BANK B -
- GROUP 2- 4 CONTROL - GROUP 1- 4 BANK C
- GROUP 2- 4 CONTROL GROUP 1 - 4 BANK D
- GROUP 2- 4 ,
l
. 48 Figure 1. FNP Arrangements of Mechanism Banks and Groups
9 MAIN CONTROL ROOM CONTROLS o IN-HOLD-0VT LEVEL o BANK SELECTOR SWITCH MANUAL AUTO-
- SHUTDOWN BANK A, B
- CONTROL BANK A, B, C, D
[ c STEP CCUNTERS l
SHOW DEMANDED POSITION o IN-0UT LIGHTS o STARTUP PUSHBUTTON o ALARM RESET PUSHBUTTON o LIFT C0Il DISCONNECT SWITCHES o ANNUNCIATORS ROD CONTROL URGENT ALARM ROD CONTROL NON-URGENT ALARM FIGURE 2
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URGENT ALARM - POWER CABINET o REGULATION FAILURE o PHASE FAILURE o LOGIC ERROR o MULTIPLEXING ERROR o CARD MISSING URGENT ALARM - LOGIC CABINET o SLAVE CYCLER RECEIVES A G0 PULSE DURING A STEP o OSCILLATOR FAILURE .
o CARD MISSING URGENT ALARM EFFECT ON SYSTEM o AUTOMATIC ROD MOVEMENT iS STOPPED o MANUAL MOVEMENT OF SELECTED BANK IS PERMITTED IF LOGIC CABINET AND POWER CABINET ARE NOT IN URGENT ALARM NON-URGENT ALARM - LOGIC OR POWER CABINET o REDUNDANT POWER SUPPLY FAILURE FIGURE 6 1
_ _ _ _ _ _ - _ _ _ _ _ - _ _ _ _ _ _ _ _ _ _ _ - _ _ _ - - _ _ . _ _ _ _ _ _ _ _ _ _ _ _]
HOW TO DISTINGUISH BETWEEN CONTROL SYSTEM AND MECHANISM PROBLEMS l
0 URGENT ALARM - MUST BE CONTROL SYSTEM FAILURE o NO URGENT ALARM, ONE OR MORE RODS WON'T MOVE MONITOR C0ll CURRENTS CONTROL SYSTEM WON'T VARY CURRENTS -
PROBLEM M.UST BE IN CONTROL SYSTEM
- CONTROL SYSTEM VARIES CURRENT TO COILS NORMALLY - SUSPECT MECHANISM
, - CURRENTS ABNORMAL GROSSLY ABNORMAL - SUSPECT CONTROL SYSTEM
- MI!.DLY ABNORMAL - SUSPECT MECHANISM FIGURE 7