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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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- Dave Morey S:uthern Nuclear
. Vece President Op: rating Compa y Farley Project P.O. Box 1295 Birmingham. Alabama 35201 Tel 205.992.5131 SOUTHERNkh October 12, 1998 COMPANY Energy to Serve %urWorld" Docket Numbers: 50-348 10 CFR 50.90 50-364 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555 Joseph M. Farley Nuclear Plant Technical Specification Change Request For Steam Generator Replacement Project - Administrative Contrcl.s Ladies and Gentlemen:
In accordance with the provisions of 10 CFR 50.90, Southern Nuclear Operating Company (SNC) proposes to amend the Farley Nuclear Plant (FNP) Unit 1 and Unit 2 Technical -
Specifications (TS), Appendix A to Operating Licenses NPF-2 and NPF-8. This TS change request will revise Section 6, " Administrative Controls," of the current Farley Unit I and Unit 2 7j TS. The proposed change consists of the recognition of additional management positions /
associated with the steam generator replacement project and providing them the ability to approve ' /
procedures regarding this project which may affect nuclear safety.
The required information for the proposed change is provided in the attachments to this letter. OO[
Attachment 1 is the basis for the proposed change. The supporting significant hazards evaluation pursuant to 10 CFR 50.91 is provided in Attachment 2. Based upon the analysis provided, SNC has determined that the proposed changes to the TS do not involve a significant hazards consideration as defined by 10 CFR 50.92. SNC has also determined that the proposed changes will not significantly affect the quality of the human environment. Attachment 3 includes the changed TS pages list, the marked-up changed TS pages, and the revised TS pages. The TS pages provided are in the current format. The Improved Technical Specifications proposed amendment will move this information to the FSAR. Any revisions to the Farley Final Safety Analysis Report (FSAR) required as a result of this change will be made in accordance with 10 CFR 50.71(e).
The Plant Operations Review Committee and the Nuclear Operations Review Board has reviewed 1
and approved this proposed change. Due to the nature of this proposed administrative change, NRC approval is requested as soon as possible but no later than by April 1999. This request is necessary to prevent a delay in implementing the steam generator replacement programs.
4010160210 981012 ~T PDR ADOCK 05000348-p PDR
1 U.S. Nuclear Regulatory Commission Page 2 l
1-L A copy of the proposed changes has been sent te Dr. D. E. Williamson, the Alabama State Designee, in accordance with 10 CFR 50.91(b)(i).
Mr. D. N. Morey states that he is a Vice President of Southern Nuclear Operating Company and is authorized to execute this oath on behalf of Southern Nuclear Operating Company and that, to the best of his knowledge and belief, the facts set forth in this letter and enclosures are true.
If you have any questions, please advise.
Respectfully submitted, SOUTHERN NUCLEAR OPERATING COMPANY b
Dave Morey Sworn to andsubscribe before me this ay of Ab . I998.
Mut/o 02,b Notary Pubdc U My Commission Expires: / ,. Md /
JMG/ CHM / cit: managers. doc Attachments: 1 Description of Proposed Amendment 2 Significant Hazards Evaluation 3 Technical Specification Changed Pages cc: Mr. L. A. Reyes, Region II Admirastrator Mr. J. I. Zimmerman, NRR Project Manager Mr. T. P. Johnson, Plant Sr. Resident Inspector Dr. D. E. Williamson, Alabama State Department of Public Health l
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Joseph M. Farley Nuclear Plant i Technical Specification Change Request For Steam Generator Replacement Project- Administrative Controls Basis for Proposed Change l
__ _ . _ _ = _ - _ _ _ _ . _ . _ _ _ _ _ _ _ . . .. . . . . ._ .. _ _. _ _ . _ _ _ _ .
Joseph M. Farley Nuclear Plant l Technical Specification Change Request For
' Steam Generator Replacement Project - Administrative Controls Basis for Pronosed Change During 1997 Southern Nuclear Operating Company (SNC), as operator of the Joseph M. Farley l
Nuclear Plant (FNP), recommended to the owner of the facility, Alabama Power Company, that
! the steam generators be replaced. Alabama Power Company approved this recommendation, and SNC put together a management team to ensure project completion. The Steam Generator Replacement Project is composed of a project manager and other management and stafTcurrently l located at the SNC corporate headquarters in Birmingham, Alabama as well as on site at FNP.
The steam generator replacement project organization has multiple reporting relationships, but reports to the General Manager - Nuclear Plant, as members of the plant staff, pursuant to that position's responsibilities for the overall unit's operation (TS 6.1.1). To facilitate an appropriate level of review and approval of the procedures necessary to conduct this activity without impacting the current operational attention of the on-site plant management, SNC is proposing to revise the list of managers that may approve procedures which may affect plant nuclear safety to include the steam generator replacement project managers.
1 The change is administrative in nature. This proposed change will have no impact on the current operation oithe FNP. Only pages in Section 6.0, " Administrative Controls," are proposed to be l changed.
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Attachment 2 Joseph M. Farley Nuclear Plant Technical Specification Change Request For Steam Generator Replacement Project - Administrative Controls Significant Hazards Evaluation
L i Joseph M. Farley Nuclear Plant Technical Specification Change Request For Steam Generator Replacement Project - Administrative Controls
. i l Significant Hazards Evaluation ,
PROPOSED CHANGE: ,
The proposed change to the Joseph M. Farley Nuclear Plant (FNP) Technical Specifications (TS) I reflects only changes to administrative controls. The change will revise the list of managers that can approve procedures which may affect plant nuclear safety.
BACKGROUND:
The Steam Generator Replacement (SGR) Project is composed of a project management and staff currently located at the SNC corporate headquarters in Birmingham, Alabama as well as on site at I l FNP. To facilitate an appropriate level of review and approval of the procedures necessary to i conduct this activity without impacting the current operational attention of the on-site plant management, SNC is proposing to add the steam generator replacement managers to the appropriate TS list. The specific positions being added to the TS list are the SGR Project l' i Manager, SGR Engineering Manager, SGR Installation Manager, SGR Quality Manager, and SGR Project Controls Manager.
, This proposed change will have no impact on the current operation of FNP. Only pages in Section 6.0, " Administrative Controls," are proposed to be revised.
I ANALYSIS:
Southern Nuclear Operating Company has reviewed the requirements of 10 CFR 50.92 as they l - relate to the identified proposed change to the FNP TS and considers this change not to involve a significant hazards consideration. In support of this conclusion, the following analysis is provided:
(1) The proposed changes do not significantly increase the probability or consequences of an accident previously evaluated in the FSAR. The proposed changes have no impact on the probability of an accident. The change being proposed is administrative in nature and involves no physical alteration of the plant or changes to setpoints or operating parameters.
i The change will provide an appropriate level of review and approval of procedures related i to the FNP steam generator replacement without impacting the operational attention of the current on-site plant management. There is no change in the FNP design basis as a result of
, this change and, as a result, does not involve a significant increase in the consequences of an accident previously evaluated.
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!- Joseph M. Farley Nuclear Plant
. Technical Specification Change Request For l - Steam Generator Replacement Project - Administrative Controls Significant Hazards Evaluation l l'
(2) The proposed changes to the TS do not increase the possibility of a new or different kind of
, accident than any accident already evaluated in the FSAR. No new limiting single failure or l accident scenario has been created or identified due to the proposed changes. Safety-related systems will continue to perform as designed. The proposed changes do not create the possibility of a new or different kind of accident from any previously evaluated.
(3) The proposed changes do not involve a significant reduction in the margin of safety. Adding l
individuals with the appropriate knowledge base to the list ofindividuals who can approve procedures, which may affect plant nuclear safety, is administrative in nature. There is no l
impact on the accident analyses. The training and experience requirements for the newly designated management positions are similar to those requirements for other FNP l management positions. Therefore the established level of procedure review and approval is not adversely impacted. In addition, these changes allow FNP management to remain i focused on plant operations. Thus the proposed changes do not involve a significant reduction in the margin of safety.
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! CONCLUSION:
Based upon the analysis provided herein, Southern Nuclear Operating Company has determined l that the proposed changes to the FNP TS will not significantly increase the probability or j consequences of an accident previously evaluated, create the possibility of a new or different kind i of accident from any accident previously evaluated, or involve a significant reduction in the j margin of safety. Therefore, Southern Nuclear Operating Company has determined that the l proposed changes rneet the requirements of 10 CFR 50.92(c) and do not involve a significant l hazards consideration.
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Attachment 3 Joseph M. Farley Nuclear Plant Technical Specification Change Request For Steam Generator Replacement Project- Administrative Controls Technical Specification Pages Technical Specifications Pages for Unit 1 - Changed Pages List Technical Specifications Pages for Unit 1 - Marked-up Pages Technical Specifications Pages for Unit 1 - Typed Pages Technical Specifications Pages for Unit 2 - Changed Pages List Technical Specifications Pages for Unit 2 - Marked-up Pages Technical Specifications Pages for Unit 2 - Typed Pages l