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Category:OPERATING LICENSES-APPLIATION TO AMEND-RENEW EXISTING
MONTHYEARML20212C5831999-09-15015 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 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 ML20063M0051994-02-16016 February 1994 Application for Amends to Licenses NPF-2 & NPF-8,proposing Changes to TS to Allow Fuel Reconstitution,To Allow Use of ZIRLO Clad Fuel & to Remove Unnecessary Detailed Descriptions of Fuel & Control Rod Assemblies ML20067B9681994-02-15015 February 1994 Suppls 931124 Application for Amends to Licenses NPF-2 & NPF-8 Re Relocation of Reactor Trip & ESFAS Response Time Limits,Per Guidance in Final Form of GL 93-08, Relocation of TS Tables of Instrument Response Time Limits ML20058J5531993-12-0909 December 1993 Application for Amend to License NPF-2,revising TS 3/4.4.6, SGs & Associated Bases & TS 3/4.4.9, Specific Activity & Associated Bases for Use of 2 Volt Interim Repair Criteria for Next Refueling Outage Scheduled for Spring of 1994 1999-09-15
[Table view] Category:TEXT-LICENSE APPLICATIONS & PERMITS
MONTHYEARML20212K9531999-10-0101 October 1999 Amends 144 & 135 to Licenses NPF-2 & NPF-8,respectively, Revising TS Nis SRs to Adjust Nis Pr Channels Only When calorimetric-calculated Power Greater than Pr Indicated Power by More than +2% RTP 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 ML20211B8761999-08-17017 August 1999 Amend 143 to License NPF-2,changing Unit 1 License in Response to Application Dtd 990423,by Adding Addl Condition Which Allows Operation of Unit 1 for Cycle 16 Based on risk- Informed Approach to Evaluate SG Tube Structural Integrity 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 ML20206L4451999-05-10010 May 1999 Amends 142 & 134 to Licenses NPF-2 & NPF-8,respectively, Changing TS 3/4.4.9, Specific Activity & Associated Bases to Increase Limit Associated with Dose Equivalent I-131 ML20203J0561999-02-19019 February 1999 Amends 107 & 85 to Licenses NPF-2 & NPF-8,respectively, Revising Section 6, Administrative Controls ML20196J4441998-12-0808 December 1998 Amends 140 & 132 to Licenses NPF-2 & NPF-8,respectively, Changing TSs to Revise Intermediate Range Neutron Flux Reactor Trip Setpoint & Allowable Valus & Delete Ref to Reactor Trip Setpoints in TS 3.10.3 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 ML20155H4771998-11-0303 November 1998 Amends 139 & 131 to FOLs NPF-2 & NPF-8,respectively,changing TSs to Revise SRs for Auxiliary Building & SW Building Batteries to Remove Existing 1.75 Volt Min Individual Cell Voltage Associated with Svc Test Acceptance Criterion ML20154L2731998-10-15015 October 1998 Amends 138 & 130 to Licenses NPF-2 & NPF-8,respectively, Changing TSs to Change Applicable Modes for Source Range Nuclear Instrumentation (TS 3/4.3.1, Reactor Trip Sys Instrumentation) 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 ML20217P0471998-04-29029 April 1998 Amends 137 & 129 to Licenses NPF-02 & NPF-08,respectively, Change Max Reactor Core Power Level for Facility Operation from 2652 Mwt to 2775 Mwt for Plants.Amends Also Approve Changes to TS to Implement Uprated Power Operation ML20216C1651998-04-0909 April 1998 Amends 136 & 128 to Licenses NPF-2 & NPF-8,respectively, Revising pressure-temp Limit Heatup & Cooldown & Hydrostatic Testing Curves 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 ML20203B4521998-02-0505 February 1998 Amends 135 & 127 to Licenses NPF-2 & NPF-8,respectively, Changing Number of Allowable Charging Pumps Capable of Injecting Into RCS When Temp of One or More Cold Legs Equal to or Less than 180F ML20203B7501998-02-0505 February 1998 Amends 134 & 126 to Licenses NPF-2 & NPF-8,respectively, Change TS 3.9.13 by Adding Footnote to Clarify Required Electrical Power Sources for Penetration Room Filtration Sys When Aligned to SFP Room During Refueling Operations ML20199F8751998-01-23023 January 1998 Amends 133 & 125 to Licenses NPF-02 & NPF-08,respectively, Changing Plant TS to Incorporate Requirements Necessary to Change Basis for Prevention of Criticality in FSP 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 ML20212F4621997-10-23023 October 1997 Amend 131 to License NPF-2,reducing Number of Required Incore Detectors Necessary for Continued Operation for Reminder of Cycle 15 Only ML20212A2221997-10-17017 October 1997 Amends 130 & 123 to Licenses NPF-2 & NPF-8,respectively, Changing TS for Both Farley Units to Allow Operability Testing for Certain Containment Isolation Valves During Defueled Status 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 ML20217E8231997-10-0101 October 1997 Amends 129 & 122 to Licenses NPF-2 & NPF-8,respectively, Revising TS to Clarify That Testing of Each Shared EDG 1-2A & 1C,to Comply W/Surveillance Requirement 4.8.1.1.2.e,only Required Once Per 5 Yrs on Per EDG Basis 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 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 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 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 ML20141F2391997-05-19019 May 1997 Amend 128 to License NPF-2,changing TS 3/4.4.9 & Associated Bases to Reduce Limit Associated W/Dose Equivalent I-131 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 ML20137E2621997-03-25025 March 1997 Amends 126 & 120 to Licenses NPF-2 & NPF-8,respectively, Revising Listed TSs & Associated Bases to Remove Certain cycle-specific Parameter Limits from TSs & Relocating to COLR 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 ML20137D6751997-03-24024 March 1997 Amend 124 to License NPF-2,revising TS 3/4.4.6, Steam Generators & Associated Bases to Implement voltage-based Alternate Repair Criteria for Steam Generator Tubes 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 ML20134F3611997-02-0303 February 1997 Amends 123 & 118 to Licenses NPF-02 & NPF-08,respectively, Replacing Containment Sys TS 3.6.2.2 for Spray Additive Sys W/New ECCS TS 3.5.6 for ECCS Recirculation Fluid Ph Control Sys 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 ML20129K3761996-11-20020 November 1996 Amend 117 to License NPF-8,changing TS to Allow Installation of Laser Welded Elevated Tubesheet Sleeves 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 ML20115J9241996-07-19019 July 1996 Amends 120 & 112 to Licenses NPF-2 & NPF-8,respectively, Approving Unit Cycle Specific TS Change to Note 4 of Table 4.3-1 That Permits Continued Operation of Both Units W/O Performing Required Serveillance of Manual Safety Infection 1999-09-15
[Table view] |
Text
Malling Address Alab ma Dower Company 600 North 18th Strest
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' Post Offre Box 2641 Birminghsm. A;abama 35291 Telephone 205 783-6081 F, L. Clayton, Jr.
Rg',g*P';ga' Alabama Power the souttwn e'ecirc system Docket Nos. 50-348 50-364 m
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Director of Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission
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qg Washington, D. C.
20555 W 64 00 k
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Attention: Mr. A. T. Schwencer Mr. S. A. Varga MN o
E Gentlemen:
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TEMPORARY CHANGE TO OPERATING LICENSE N0. NPF-2 AND NPF-8 TECHNICAL SPECIFICATIONS As reported by Promot Report on Manch 24, 1981, it has been deter-mined (based on recently ecopleted flow testing for the Farley Unit 2 river water system) that under a postulated accident condition involving the extremely unlikely event of a service water pond dam break coupled with the single most limiting active failure (e.o, loss of one train of river water), the time stipulated in the FSAR for operator action is not avail-able. This situation is applicable only when both units are operating.
FSAR Section 9.2.1.3 states that there will be 30 minutes following a loss of pond dam and loss of one train of river water before the operator is required to taKe action to balance service water requirements With river water supply.
Based on th, f. low tests, the operator will have approximately 20 minutes available to take action to balance service water flow with river water flow when both units are operating and the postulated accident conditions occur.
In order to restore the cime available for operator action, Alabama Power Company will make available an additional source of water to the service water pumps under these conditions. This will be accomplished by the addition of a safety grade 36" line running from the two existing 60" service water recirculation lines (service water return to pond) directly into the service water wet pit.
(See Figure 1 for schematic of line addition.) Under the accident conditions described in FSAR Section 9.2.1.3, recirculation of service water directly to the service water structure wet pit via the two 60" return lines and the new 36" line would be automatically initiated.
This modification will ensure a period of time substantially in i
excess of 30 minutes before operation action would be required to balance 810 3 3109W f
Director of Nuclear Reactor Regulation March 24, 1981 U. S. Nuclear Regulatory Commission Page 2 service water requirements with river water supply. The completion of this modification is currently scheduled for May 15, 1981.
Alabama Power Company proposes to operate both units in Modes 1 through 4 prior to completing'this modification.
Unit 1 is in the process of returning from refueling operations and is scheduled for full power operation during the week of March 30, 1981.
Unit 2 is presently in initial startup sequence and is scheduled to enter Mode 4 on or about April 4,1981 and Mode 1 on or about May 6, 1981.
This course of action is based on the following:-
1.
It is extremely unlikely that a dam failure at Farley Nuclear Plant will occur because of the following:
a.
The dam is conservatively designed and constructed to withstand the design basis seismic event selected for the site. The acceleration levels assumed for the design basis earthquake are conservative since Farley Nuclear Plant is located in one of the lowest seismic regions of the United States as stated:in FSAR Section 2.5.
b.
The dam is conservatively designed and constructed to withstand the probablemaximum flood postulated to occur at l
the site coupled with the wave heights that could be reached for extremely high wind levels.
2.
The accident scenario also requires loss of one train of river water. This in and of itself is unlikely within the short time period of the modification.
3.
Operators will receive additional emphasis on the specific actions required to balance service water flow undar the postulated accident conditions.
4.
Upon entering Mode 1, Unit 2 uill be performing power range testing at lou to intermediate power levels and no appreciable decay heat would be generated prior to the scheduled conpletion
=
of the modification.
Alabama Power Company has determined that no unreviewed safety question will exist as a result of implementation of this modification.
Implementation of this modification will require voluntary entry into limiting conditions for operation (LC0's) for both units for the service water system while the return lines to the pond are being modified to install the line to the service water pump wet pit. This work is estimated to require the cc. rent technical spe' :fication ti.,e limit of 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> for service water train inoperability without further action to be exceeded while the return lines to the pond are being modified.
4
. ~ _,
Director of Nuclear Reactor Regulation March 24, 1981 U. S. Nuclear Reguiatory Commission Page 3 It is requested that a temporary change to the Farley Units i i2 Technical Specifications Section 3.7.4 be granted to allo,s Alat ser Company's Farley Unit I and Unit 2 to be in Modes 1 through 4 c ing the period of time associated with the modification requiring the voluntary LCO. -This period of time will be no longer than 10 days for each train (e.g., only one train will be modified at-a time). Attached is the requested technical specification change with bases. Alabama Power Company plans to initiate the modification requiring the temporary change on April 10, 1981 and requests approval prior to this date.
The Plant Operations Review Committee and the Nuclear Operations Review Board have reviewed the above proposed changes and have determined that the changes do not involve an unreviewed safety question as shown in the attached safety evaluation.
The class of each item in this proposed amendment is designated as Class III for Unit 1 and Class I for Unit 2 according to 10 CFR 170.22 requirements.
Enclosed is a check for $4,400 to cover the total amount of fees required.
In accordance with 10 CFR 50.30(c)(1)(i), three signed originals and thirty-seven additional copies of these proposed changes are enclosed.
If you have any questions, please advise.
Yours very truly, l
sF. L. Clayton, Jr.
FLCjr/CLB:de Attachments SWORN TO AND SUBSCRIBED BEFORE ME Ty,IS,7.f DAY pfj cc: Mr. J. P. O'Reilly
/7/Niv//
, 19 4/
Mr. R. A. Thomas Mr. G. F. Trowbridge Mr. E. A. Reeves
)
1 Mr. L. L. Kintner
/
Mr. W. H. Bradford
~
NotaryPublip My Commission Expires:
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Figure 1 - Modification to Farley Nuclear Plant Service Water Recirculation System I
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Figure 1-Attachment During normal operation,' river water valves 1 and 2 are closed and normal flow is to the pond through valves 3 and 4.
Service water is supplied to the plant and discharged to the river through valves 7 and 9 for Unit 1 and valves 8 and 10 for Unit 2.
The pond recirculation valves 5 and 11 for Unit 1 and valves 6 and 12 for Unit 2 are closed. The proposed valves 13 and 14 are opened and valves 15 and 16 are closed.
For the failure modes and effects analysis, the following scenario is assumed to occur instantaneously:
1.
Loss of pond dan 2.
Loss of off-site power 3.
Loss of control air 4.
Horst case single fai'1 9 of loss of one train of river water due to failure of either valves 1 and 3 or 2 and 4 to divert river water to the service water wet pit.
When this scenario occurs, the service water flow out of the wet pit exceeds the river water nake-up to the wet pit.
The stoplogs in the service water wet pit are at elevation 180'-0".
Upon reaching 179'-6", train "A" and train "B" level switches will open the valves 5, 6,11,12,15 and 16 and
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valves 7, 8, 9 and 10 will close. Valves 13 and 14 will close to a throttled position such that a portion of the flow will tua diverted to the service water wet pit and a portion to the pond.
fiOTE: The system is designed such that one train of recirculation flow will provide the necessary flow to the service water wet pit to extend the operator action time to greater than 30 minutes. At this time the operator will take action to balance service water requirements with the river water flows and restore the service water valves to the normal configuration.
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