|
---|
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
..
- . . - _ . - - - - - = - .- - - - - - - -
Southern Nuclear Operating Company i
[
, Post Office Box 1295 l
, a Birmingham. Alabama 35201 i Telephone (205) 868-5086 l
i n
- s. o. wooo.,o Southern Nudear Operating Company Executive %ce President October 20, 1994 Docket Nos. 50-348 10 CFR 50.90 50-364 U.S. Nuclear Regulatory Commission A T rN.: Document Control Desk Washington, D.C. 20555 Joseph hi. Farley Nuclear Plant Deletion of Chlorine Detection System Gentlemen:
The Joseph hi. Farley Nuclear Plant Technical Specifications contain requirements for operation of a chlorine detection system. As a result of the removal of all large, i.e., containing more than 150 pounds, chlorine storage containers from the plant site, there is no safety or regulatory requirement to maintain the Chlorine Detection System. As a result, Southem Nuclear Operating Company is proposing to delete the technical specification requirements for the Chlorine Detection System.
l Enclosure 1 provides a description of the proposed change and the bases for the change requests.
Enclosure 2 provides the basis for a determination that the proposed change does not involve a significant hazards consideration. Enclosure 3 contains the proposed changed Technical l
Specification pages in ::uppert of the amendment. Southern Nuclear has determined that the
- proposed license amendment will not significantly affect the quality of the environment.
t If there are any questions, please advise.
Respectfully submitted, b
J. D. Voodard l
. REhi/ cit:CIILORNRC. DOC Enclosures SWORN TO AND SUBSCRIBED BEFORE h1E cc: hir. S. D. Ebneter THIS DAY OF hb[Gi 1994 l
IErN.$ 'ss' Dr. D. E. Williamson b M.Nd j ' blic u
1 v
_ ,, c .
hiy Con 1 mission Expires: b/Nf[
~uv, ( ,
9410260050 941020 PDR l ADOCK 05000348 i P PDR hsj j
a , ,
l l
Enclosure 1
\
Technical Specification Amendment for Deletion of Chlorine Detection System j i
Safety Analysis for Proposed Change '
I 1
l l
)
. \
Technical Specification Amendment for Deletion of Chlorine Detection System Safsty Analysis for Proposed Change i l
! Proposed Change l Technical Specification 3/4.3.3.6 and its associated basis provide for the operation of a Chlorine Detection l System in accordance with Regulatory Guide 1.95. The proposed Technical Specification changes will delete requirements for the Chlorine Detection Systems from Units 1 and 2 Technical Specifications.
Basis l
Stored gaseous chlorine, except for containers having an inventory of 150 pounds or less, have been j removed from the Farley Nuclear Plant site and replaced by chlorine compounds in alternative fonns which l maintain the desired level of dissolved chlorine in the treated water but preclude the need for storage of large amounts of gaseous chlorine. A small amount of gaseous chlorine (150 pound bottles) will be kept in a chlorination house as a backup for the hypochlorite system and the failure of one container will not lead to the release of multiple containers. This chlorination house is located more than 100 meters from the control room and its fresh air inlets. Funhermore, manual isolation of the control room is provided by existing hand switches for thore valves in which the automatic chlorine isolation signal is being removed.
The removal of the gaseous chlorine and deletion of the chlorine detection system is in compliance with the requirements of Regulatory Guide 1.95, " Protection of Nuclear Power Plant Control Room Operators Against an Accidental Chlorine Release," dated February,1975. This Regulatory Guide allows for the presence of chlorine containers having an inventory of 150 pounds or less provided that the chlorine is stored more than 100 meters from the Control Room, the capability for manual isolation of the Control
! Room is provided, and, if more than one container is present, the containers are interconnected in such a manner that failure of a single container will not cause release from several containers.
Farley Nuclear Plant is committed to the requirements of Regulatory Guide 1.78, " Assumptions for ,
Evaluating the Habitability of a Nuclear Power Plant Control Room During a Postulated Hazardous l
Chemical Release," June,1974. This Regulatory Guide identifies chlorine as a potentially hazardous chemical which, if released in sufTicient quantities, could result in the control room becoming l uninhabitable. The Regulatory Guide provides guidance that hazardous chemicals stored or situated at distances greater than 5 miles need not be considered since, in the case of an accidental release, there ;
j should be sufficient time for the control room operators to take appropriate action. If hazardous chemicals l are known or projected to be frequently shipped by rail, water or road routes within a five mile radius of a j nuclear power plant, estimates of these shipments should be considered in the evaluation of control room
! habitability. In addition, hazardous chemicals (chlorine) stored on the nuclear plant site should be accompanied by instrumentation that will detect its escape, set off an alarm and provide a readout in the
- control room. However, based on Regulatory Guide 1.95, " Protection of Nuclear Power Phnt Control l Room Operators Against an Accidental Chlorine Release," instrumentation (either local or remote) is not I
required if onsite chlorine storage is limited to 150 pounds or less stored more than 100 meters from the control room or its fresh air inlets.
Commercial barge traffic occurs within 1 mile of the control room. An average ofless than 250 barges pass Farley Nuclear Plant cach year. The main products transported by barge through the Columbia Lock and Dam are chemicals (chlorine gas is not included), diesel fuel, gasoline, oil, dredging equipment, pipelines, fertilizer, antifreeze, liquid feed, corn and soybeans, and steel. The nearest road to the plant is Alabama Route 95 located less th2m a mile from the control room. There are no known regular shipments 1
)
Deletion of Chlorine Detection System Page 2 Safety Analysis of chorine on this road. The Central of Georgia Railroad, passing about 5 miles north of the plant, has one freight train making one round trip daily. Based on estimated frequency and size of shipments, an evaluation of the effect on plant operation of potential accidents in either a barge, truck or railroad car located at their closest points of approach concluded that accidents on these transportation routes would not affect the safe operation of the plant. Currently, no chlorine gas is processed at, stored at, or transported to or from any of the industrial facilities located within 5 miles of the plant. Based on the distances of these facilities from the plant and the types and quantities of materials used and stored in such facilities, it has been concluded that an accident at one of these facilities would not constitute a hazard to the safe operation of the plant.
As previously evaluated and recently confinned, there are no identified chlorine hazards to the plant posed by commercial facilities or nearby transportation modes. This evaluation was performed with regard to Regulatory Guides 1.78 and 1.95. Protection of the control room against accidental chlorine releases was provided solely to guard against the accidental release of chlorine stored on-site. Thus, since on-site sources of gaseous chlorine have been reduced to 150 pound containers or removed, there are no concerns regarding potential chlorine hazards to the control room and the chlorine detection system is no longer required for protection of control room personnel.
I l
l l
i 1
I i
l l
1
F l
l .
I l
! Enclosure 2 l
t l
I t
l l
Technical Specification Amendment for Deletion of Chlorine Detection System Significant Hazards Evaluation I
Joseph M. Farley Nuc! car Plant Unit I and Unit 2 Deletion of Chlorine Detection System 10 CFR 50.92 EVALUATION Pursuant to 10CFR50.92, Southem Nuclear Operating Company (SNC) has evaluated the deletion of the chlorine detection system technical specification requirements from the Farley Nuclear Plant
! Units I and 2 Technical Specifications and has detennined that operation of the facility in accordance with the proposed amendment would not involve significant hazards considerations.
Backaround Technical Specification 3/4.3.3.6 and its associated basis provide for the operation of a Chlorine Detection System in accordance with Regulatory Guide 1.95. The proposed Technical Specification changes will delete requirements for the Chlorine Detection Systems from Units I and 2 Technical Specifications. l Stored gaseous chlorine, except for containers having an inventoy of 150 pounds or less, have
, been removed from the plani site and replaced by chlorine compounds in alternative fonns which l maintain the desired level of dissolved chlorine in the treated water but preclude the need for storage oflarge amounts of gaseous chlorine. A small amount of gaseous chlorine (150 pound bottles) will be kept in a chlorination house as a backup for the hypochlorite system. This chlorination house is located more than 100 meters from the control room and its fresh air inlets.
Furthermore, manual isolation of the control room is provided by existing hand switches for those valves in whie the automatic chlorine isolation signal is being removed.
The removal of the gaseous chlorine and deletion of the chlorine detection system is in compliance with the requirements of Regulatory Guide 1.95, " Protection of Nuclear Power Plant Control Room Operators Against an Accidental Chlorine Release," date,i February,1975. This Regulatory Guide allows for the presence of chlorine containers having an inventory of 150 pounds or less provided that the chlorine is stored more than 100 meters from the Control Room, the capability for manual isolation of the Control Room is provided, and, if more than one container is present, the containers are interconnected in such a manner that failure of a single container will not cause l release from several containers.
l Analvsis l
! Farlev Nuclear Plant is committed to the requirements of Regulatory Guide 1.78, " Assumptions for i Evaluating the Habitability of a Nuclear Power Plant Control Room During a Postulated l liazardous Chemical Release," June,1974. This Regulatory Guide identifies chlorine as a potentially hazardous chemical which, if released in suflicient quantities, could result in the control room becoming uninhabitable. The Regulatory Guide provides guidance that hazardous chemicals stored or situated at distances greater than 5 miles need not be considered since, in the case of an accidental release, there should be sufficient time for the control room operators to take appropriate action. If hazardous chemicals are known or projected to be frequently shipped by rail, water or road routes within a five mile radius of a nuclear power plant, estimates of these shipments should be considered in the evaluation of control room habitability. In addition, hazardous chemicals (chlorine) stored on the nuclear plant site should be accompanied by instrumentation that will detect its escape, set off an alarm and provide a readout in the control room. However, based on Regulatory Guide 1.95," Protection of Nuclear Power Plant Control Room Operators Against an
Deletion of Chlorine Detection System Page 2 10 CFR 50.92 Evaluation Accidental Chlorine Release," instrumentation (either local or remote) is not required if onsite chlorine storage is limited to 150 pounds or less stored more than 100 meters from the control room or its fresh air inlets.
Commercial barge traffic occurs within 1 mile of the control room. An average ofless than 250 barges pass Farley Nuclear Plant each year. The main products transported by barge through the Columbia Lock and Dam are chemicals (chlorine gas is not included), diesel fuel, gasoline, oil, dredging equipment, pipelines, fertilizer, antifreeze, liquid feed, corn and soybeans, and steel. The nearest road to the plant is Alabama Route 95 located less than a mile from the control room.
There are no known regular shipments of chorine on this road. The Central of Georgia Railroad, passing about 5 miles north of the plant, has one freight train making one round trip daily. Based on estimated frequency and size of shipments, an evaluation of the effect on plant operation of potential accidents in either a barge, truck or railroad car located at their closest points of approach concluded that accidents on these transportation routes would not affect the safe operation of the plant. Currently, no chlorine gas is processed at, stored at, or transported to or from any of the industrial facilities located within 5 miles of the plant. Based on the distances of these facilities from the plant and the types and quantities of materials used and stored in such facilities, it has ,
been concluded that an accident at one of these facilities would not constitute a hazard to the safe operation of the plant.
As previously evaluated and recently confirmed, there are no identified chlorine hazards to the plant posed by commercial facilities or nearby transportation modes. This evaluation was
]
performed with regard to Regulatory Guides 1.78 and 1.95. Protection of the control room against -
accidental chlorine releases v as provided solely to guard against the accidental release of chlorine stored on-site. Rus, since on-site sources of gaseous chlorine have been reduced to 150 pound i containers or removed, there are no concerns regarding potential chlorine hazards to the control room.
Results Based on the information presented above, the following observations are made with respect to 10 CFR 50.92 for removal of the chlorine detection systems.
- 1. Removal of the control room chlorine detection system does not involve a significant increase in the probability or consequences of an accident previously evaluated because on-site gaseous chlorine will be limited to a maximum per container inventory of 150 pounds located greater than 100 meters from the control room and manual isolation of the s
control room is provided. This is in compliance with Regulatory Guide 1.95.
Furthermore, offsite chlorine storage and transportation meets the requirements of Regulatory Guides 1.78 and 1.95. Therefore, the probability of occurrence of an accident is not affected.
There are no radiological consequences associated with chlorine release accidents.
Therefore, the consequences of an accident previously evaluated are not increased.
- 2. Removal of the control room chlorine detecM , system does not create the possibility of a new or different kind of accident from any accident previously evaluated since the chlorine detectors are utilized for detection of accidental chlorine release and are not accident initiators. Gascous chlorine has been removed from the plant site, except for a permissible
Deletion of Chlorine Detection System Page 3 10 CFR 50.92 Evaluation maximum per container inventory of 150 pounds which will be located greater than 100 meters away from the control room. In addition, there is a provision for the manual isolation of the control room. Therefore, on-site chlorine storage meets the requirements of Regulatory Guide 1.95. Furthermore, ofTsite chlorine storage and transportation meet the requirements of Regulatory Guides 1.78 and 1.95.
- 3. Removal of the control room chlorine detection system does not involve a significant reduction in the margin of safety related to the protection of control room operators from excessive levels of chlorine since the onsite chlorine storage will be limited to a maximum l per container inventory of 150 pounds at the chlorination house, which is located greater than 100 meters from the control room. In addition. rcanual isolation of the control room is also provided. This meets the requirements of Regulatory Guide 1.95. Therefore, onsite and offsite chlorine storage and transportation meets the requirements of Regulatory Guides 1.78 and 1.95.
j Conclusions l
l Based on the preceding analysis, it has been concluded that the proposed Technical Specifications l changes to remove the chlorine detection system do not involve a significant increase in the l probability of consequences of an accident previously evaluated, create the possibility of a new or l different kind of accident from any accident previously evaluated, or involve a significant reduction in a margin of safety. Therefore, the proposed changes do not involve a significant hazard in accordance with 10 CFR 50.92.
Enclosure 3 t
1 Revised Technical Specification Pages (Marked up pages with changes annotated are also included.)
Unit 1 Bqsision Page IV Replace 3/4 3-52 Replace B 3/4 3-3 Replace Unit 2 Revision Page IV Replace 3/4 3-52 Replace B 3/4 3-3 Replace i