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| . Washington, D.C. 20555 Attention: Mr. S. A. Varga LJoseph M. Farley Nuclear Plant - Units 1 and 2 Proposed Technical Specification Change to D.C. Distribution System Requiremsats~ | | . Washington, D.C. 20555 Attention: Mr. S. A. Varga LJoseph M. Farley Nuclear Plant - Units 1 and 2 Proposed Technical Specification Change to D.C. Distribution System Requiremsats~ |
| . Gentlemen: | | . Gentlemen: |
| Alabama Power Company letter dated May 3,1983 proposed changes to the technical specifications regarding the Auxiliary and Service Water Building D.C. . Distribution Systems. Subsequent discussions with the NRC Staff identified the need for submittal of additional information and revision to the-May 3,:1983 proposed changes as contained herein. | | Alabama Power Company {{letter dated|date=May 3, 1983|text=letter dated May 3,1983}} proposed changes to the technical specifications regarding the Auxiliary and Service Water Building D.C. . Distribution Systems. Subsequent discussions with the NRC Staff identified the need for submittal of additional information and revision to the-May 3,:1983 proposed changes as contained herein. |
| Float Voltage Surveillance Requirement Alabama Power Company proposed to revise the existing float voltage surveillance requirement from a single criterion of 2.02 volts to Category B allowable of 2.02. volts and Category A and B limits of 2.07 volts. The NRC Staff indicated that the 2.02 volt value was acceptable based on previous licensing action by the NRC; however, the 2.07 volt limits were unacceptable based on the Standard Technical Specification guidance that 2.13 volt limits | | Float Voltage Surveillance Requirement Alabama Power Company proposed to revise the existing float voltage surveillance requirement from a single criterion of 2.02 volts to Category B allowable of 2.02. volts and Category A and B limits of 2.07 volts. The NRC Staff indicated that the 2.02 volt value was acceptable based on previous licensing action by the NRC; however, the 2.07 volt limits were unacceptable based on the Standard Technical Specification guidance that 2.13 volt limits |
| --were required. As discussed with the NRC Staff, Alabama Power Company hereby revises the proposed Category A and B limits to 2.02 volts in | | --were required. As discussed with the NRC Staff, Alabama Power Company hereby revises the proposed Category A and B limits to 2.02 volts in |
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| Conclusion The D.C. Distribution System proposed technical specification change, including this supplement, is considered to not involve a Significant Hazards Consideration as defined in 10CFR50.92. These changes are similar to example (ii) of " Examples of Amendments That Are Considered Not Likely to Involve Significant Hazards Considerations" listed in 48FR14870 dated April 6,1983 in that these changes involve restriction and control not presently included in the technical specifications. In addition, the proposed technical specification change conforms in general with the fomat of the | | Conclusion The D.C. Distribution System proposed technical specification change, including this supplement, is considered to not involve a Significant Hazards Consideration as defined in 10CFR50.92. These changes are similar to example (ii) of " Examples of Amendments That Are Considered Not Likely to Involve Significant Hazards Considerations" listed in 48FR14870 dated April 6,1983 in that these changes involve restriction and control not presently included in the technical specifications. In addition, the proposed technical specification change conforms in general with the fomat of the |
| :most recent Westinghouse Standard Technical Specifications (WSTS). The | | :most recent Westinghouse Standard Technical Specifications (WSTS). The |
| . differences between the currently approved WSTS and the proposed technical specification change are detailed in' Attachment 1 of the May 3,1983 letter and this supplement. The class of this proposed change was designated as | | . differences between the currently approved WSTS and the proposed technical specification change are detailed in' Attachment 1 of the {{letter dated|date=May 3, 1983|text=May 3,1983 letter}} and this supplement. The class of this proposed change was designated as |
| . Class III' for Unit 1 and Class I for Unit 2 in accordance with 10CFR170.22 requirements. :A check for $4,400 to cover the total amount of fees required was enclosed with the May 3,1983 letter. As noted by the distribution, a copy of this . supplemental letter is being sent to the Alabama State Designee in'accordance with 10CFR50.91 (b)(1). | | . Class III' for Unit 1 and Class I for Unit 2 in accordance with 10CFR170.22 requirements. :A check for $4,400 to cover the total amount of fees required was enclosed with the {{letter dated|date=May 3, 1983|text=May 3,1983 letter}}. As noted by the distribution, a copy of this . supplemental letter is being sent to the Alabama State Designee in'accordance with 10CFR50.91 (b)(1). |
| Yours very tru , , | | Yours very tru , , |
| / s | | / s |
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Category:OPERATING LICENSES-APPLIATION TO AMEND-RENEW EXISTING
MONTHYEARL-99-033, Application for Amends to Licenses NPF-2 & NPF-8,to Change TS Re Control Room,Penetration Room & Containment Purge Filtration Sys & Radiation Monitoring Instrumentation,Which Reflect Agreements Reached in 990909 & 16 Discussions1999-10-0404 October 1999 Application for Amends to Licenses NPF-2 & NPF-8,to Change TS Re Control Room,Penetration Room & Containment Purge Filtration Sys & Radiation Monitoring Instrumentation,Which Reflect Agreements Reached in 990909 & 16 Discussions ML20212C5831999-09-15015 September 1999 Application for Amends to Licenses NPF-2 & NPF-8,committing Util to Transfer Certain CTS Requirements Into Util Controlled Documents & Specifying Schedule for Performing New & Revised ITS Surveillances.Revised License Pages,Encl ML20210R5181999-08-12012 August 1999 Revised Page 6 to 990430 LAR to Operate Farley Nuclear Plant,Unit 1,for Cycle 16,based on risk-informed Approach for Evaluation of SG Tube Structural Integrity.Marked Page of Current License,Included L-99-018, Application for Amend to License NPF-2 for Approval to Operate Unit 1,cycle 16 Only,Based on risk-informed Approach for Evaluation of SG Tube Structural Integrity1999-04-30030 April 1999 Application for Amend to License NPF-2 for Approval to Operate Unit 1,cycle 16 Only,Based on risk-informed Approach for Evaluation of SG Tube Structural Integrity L-99-013, Application for Amends to Licenses NPF-2 & NPF-8.Amends Would Increase Dei Limit from 0.15 to 0.3 Uci/Gram IAW 10CFR50.90.Marked-up & Revised Current TS Encl1999-04-0202 April 1999 Application for Amends to Licenses NPF-2 & NPF-8.Amends Would Increase Dei Limit from 0.15 to 0.3 Uci/Gram IAW 10CFR50.90.Marked-up & Revised Current TS Encl ML20155J4391998-11-0606 November 1998 Application for Amends to Licenses NPF-2 & NPF-8,requesting Change to TS Nuclear Instrumentation Sys Power Range Daily Surveillance Requirement ML20154K2451998-10-12012 October 1998 Application for Amends to Licenses NPF-2 & NPF-8,revising Section 6 of TS by Recognizing Addl Mgt Positions Associated with SG Replacement Project & Providing Ability to Approve Procedures Re Project Which May Affect Nuclear Safety ML20216F7051998-03-12012 March 1998 Application for Amends to Licenses NPF-2 & NPF-8 to Revise Existing TS in Entirety.Amend Consists Primarily of Conversion of Current TS to Improved Ts,Per NUREG-1431,rev 1.Vols 1-10 Contain Listed Attachments ML20198H3561998-01-0707 January 1998 Application for Amends to Licenses NPF-2 & NPF-8,adding Note to TS to Specifically Indicate Normal or Emergency Power Supply May Be Inoperable in Modes 5 or 6 Provided That Requirements of TS 3.8.1.2 Are Satisified ML20198E6531997-12-31031 December 1997 Application for Amends to Licenses NPF-2 & NPF-8,changing Nis IR Neutron Flux Reactor Trip Setpoint & Allowable Value to Be Consistent W/W Std TS,NUREG-1431,Rev 1.Proprietary Safety Analysis,Encl.Proprietary Info Withheld ML20198E2891997-12-30030 December 1997 Application for Amends to Licenses NPF-2 & NPF-8,changing Requirements for Auxiliary Bldg & Svc Water Bldg Batteries, Per NRC Staff Concerns as Described in URI 50-348/97-201 & 50-364/97-201 & NOV 50-348/97-11 & 50-364/97-11 ML20211P5811997-10-16016 October 1997 Application for Amends to Licenses NPF-2 & NPF-8,revising Number of Allowable Charging Pumps Capable of Injecting in RCS When Temperature of One or More of RCS Cold Leg Temperatures Is Less than 180 F ML20211A6811997-09-17017 September 1997 Application for Amends to Licenses NPF-2 & NPF-8,amending Primary Coolant Specific Activity,Per GL 95-05 ML20216C9231997-09-0303 September 1997 Application for Amend to License NPF-2,allowing Reduction in Available Paths to Min of 50% w/3 Per Core Quadrant. Non-proprietary & Proprietary W Repts CAA-97-234 & CAA-97-235,encl.Proprietary Info,Withheld ML20149K0971997-07-23023 July 1997 Application for Amends to Licenses NPF-2 & NPF-8,relocating RCS P/T Limits from TS to Proposed PT Limits Rept IAW Guidance Provided by GL 96-03, Relocation of P/T Limit Curves & LTOP Protection Sys Limits ML20148R7351997-06-30030 June 1997 Application for Amends to Licenses NPF-2 & NPF-8, Incorporating Requirements Necessary to Change Basis for Prevention of Criticality in Fuel Storage Pool.Change Eliminates Credit for Boraflex as Neutron Absorbing Matl ML20148Q0981997-06-30030 June 1997 Application for Amends to Licenses NPF-2 & NPF-8,revising & Clarifying Requirements for CR Emergency & Penetration Room Filtration Sys & Related Storage Pool Ventilation Sys & Revises Radiation Monitoring Instrumentation Channels ML20148K7421997-06-13013 June 1997 Application for Amends to Licenses NPF-2 & NPF-8,proposing Changes Found in Tech Specs 3/4.9.13, Storage Pool Ventilation (Fuel Movement) ML20140A3861997-05-28028 May 1997 Application for Amends to Licenses NPF-2 & NPF-8,clarifying That Testing of Each Shared EDG to Comply W/Sr 4.8.1.1.2.e Is Only Required Once Per Five Years on a Per EDG Basis,Not on Per Unit Basis ML20148E5851997-05-27027 May 1997 Application for Amends to Licenses NPF-2 & NPF-8,revising Applicable Modes for Source Range Nuclear Instrumentation & Providing Allowances for an Exception to Requirements for State of Power Supplies for RHR Discharge to Pump Valves ML20138B9161997-04-23023 April 1997 Application for Amends to Licenses NPF-2 & NPF-8,revising Proposed TS Pages to Include Footnote Concerning Filter Pressure Drop Testing & Mechanical Heater Testing ML20137H6011997-03-25025 March 1997 Application for Amend to License NPF-2,requesting Implementation of voltage-based Alternate Repair Criteria, Per GL 95-05 ML20136F8141997-03-0707 March 1997 Application for Amends to Licenses NPF-2 & NPF-8,revising TS 3/4.6.3 Re Containment Isolation Valves Surveillance Requirements ML20135C6511997-02-24024 February 1997 Application for Amends to Licenses NPF-2 & NPF-8,requesting Revision & Clarification to Surveillance Requirements for Control Room Emergency Filtration Sys,Penetration Room Filtration Sys & Containment Purge Exhaust Filter ML20135C8311997-02-14014 February 1997 Application for Amends to Licenses NPF-2 & NPF-8,revising Specified Max Power Level & Definition of Rated Thermal Power ML20138G9451996-12-26026 December 1996 Application for Amends to Licenses NPF-2 & NPF-8,reflecting Guidance in GL 95-05, SG Tube Support Plate Voltage-Based Repair..., to Use Revised Accident Leakage Limit of 20 Gpm & Include 50% of Rpc Ndds in Calculation.W/O Unit 2 TSs ML20134K5501996-11-15015 November 1996 Application for Amends to Licenses NPF-2 & NPF-8,requesting Deletion of TS 3.6.2.2 Re Containment Spray Additive Sys ML20128F8681996-09-30030 September 1996 Application for Amends to Licenses NPF-2 & NPF-8,relocating cycle-specific Core Operating Parameter Limits to Colr. Proposed Changes Based on Guidance Found in NRC GL 88-16, WOG-90-016,NUREG-1431 & VEGP COLR Approved by NRC ML20117G2911996-08-30030 August 1996 Application for Amend to License NPF-8,requesting Deletion of References to Cycle Specific L* Criteria ML20117D2201996-08-23023 August 1996 Application for Amends to Licenses NPF-2 & NPF-8,requesting to Allow Use of Elevated Sleeve ML20113B6931996-06-24024 June 1996 Application for Amends to Licenses NPF-2 & NPF-8,deleting Requirement for Surveillance of Manual SI Input to Reactor Trip Circuitry Until Next Unit Shutdown ML20113A7991996-06-20020 June 1996 Application to Revise Ts,Reflecting Implementation of 10CFR50,App J,Option B & Represent Crossed Beneficial Licensee Actions ML20112G9711996-06-12012 June 1996 Application for Amends to Licenses NPF-2 & NPF-8,providing Improved Operating Margins as Well as Increased Flexibility W/Respect to Core Designs & Plant Operating Strategy. Rev 2 to NSD-NT-OPL-96-152 Withheld ML20107J9551996-04-23023 April 1996 Application for Amend to License NPF-8,requesting Unit 2 Cycle 11 TS Change for SG Tubes Remaining in Svc ML20107J1521996-04-22022 April 1996 Application for Amend to License NPF-8,reflecting Implementation of New F* Criteria Based on Maintaining Existing Safety Margins for SG Tube Structural Integrity Concurrent W/Allowance for NDE Eddy Current Uncertainty ML20101L9041996-03-29029 March 1996 Application for Amend to License NPF-8,revising TS 3/4.4.6, Steam Generators & Associated Bases,Reflecting Guidance in GL 95-05.Responses to GL & Revised TS Encl ML20095L0161995-12-19019 December 1995 Application for Amends to Licenses NPF-2 & NPF-8,revising Tech Specs Section 3/.7.7 Re Control Room Emergency Ventilation Sys ML20098B0911995-09-26026 September 1995 Application for Amends to Licenses NPF-2 & NPF-8,changing TS 4.6.1.3 to Incorporate Improvements to Containment Air Lock Testing Ref in Chapter 3.6,containment Sys of NUREG-1431, Sts,Westinghouse Plants ML20092F3821995-09-15015 September 1995 Application for Amend to License NPF-2 & NPF-8,eliminating Periodic Pressure Sensor Response Time Testing Requirements ML20084P4901995-05-31031 May 1995 Application for Amends to Licenses NPF-2 & NPF-8,revising TS Associated W/Steam Generator Tube Support Plate voltage- Based Repair Criteria ML20080R8201995-03-0606 March 1995 Application for Amends to Licenses NPF-2 & NPF-8,relocating Seismic & Meteorological Monitoring Instrumentation TSs to FSAR ML20078P8331995-02-14014 February 1995 Application for Amend to Licenses NPF-2 & NPF-8 Re Permanent voltage-based Repair Criteria for Outside Diameter Stress Corrosion Cracking at SG Tube Support Plates for Both Units at Plant ML20077R4071995-01-0909 January 1995 Application for Amends to Licenses NPF-2 & NPF-8, Incorporating line-item TS Improvements to Reduce Surveillance Requirements for Testing During Power Operation in Response to GL 93-05 ML20078S7531994-12-19019 December 1994 Application for Amends to Licenses NPF-2 & NPF-8,revising TS Pages for Mssv,Per NRC Information Notice 94-060, Potential Overpressurization of Main Steam Sys ML20077E3461994-12-0707 December 1994 Application for Amends to Licenses NPF-2 & NPF-8,revising TS to Reflect Guidance in Draft GL 94-XX, Voltage-Based Repair Criteria for Repair of Westinghouse SG Tubes Affected by Outside Diameter Stress Corrosion Cracking ML20078B5451994-10-20020 October 1994 Application for Amends to Licenses NPF-2 & NPF-8,proposing TS 3/4.3.3.6 & Associated Bases,Which Will Delete Requirements for Chlorine Detection Sys from Units 1 & 2 TS ML20072F3401994-08-17017 August 1994 Application for Amends to Licenses NPF-2 & NPF-8,eliminating Periodic Pressure Sensor Response Time Testing Requirements. Rev 1 to WCAP-13787 & Proprietary Rev 1 to WCAP-13632, Elimination of Pressure... encl.WCAP-13632,Rev 1 Withheld ML20070A1001994-06-17017 June 1994 Application for Amend to License NPF-2,revising TS 3/4.2.3 to Increase Nuclear Enthalpy Rise Hot Channel Factor Limit from 1.65 to 1.70 for Vantage 5 Fuel,In Order to Provide Greater Flexibility in Farley Unit 1 Core Design ML20069K2781994-06-10010 June 1994 Application for Amends to Licenses NPF-2 & NPF-8,changing RTS & ESFAS Setpoints Associated W/Sg Water Level. Westinghouse Nonproprietary & Proprietary Version of Rept, SG Lower Level Tap... Encl.Proprietary Rept Withheld ML20064C2111994-02-23023 February 1994 Application for Amend to License NPF-2,revising TS, to Allow Implementation of 2 Volt Interim Plugging Criteria 1999-09-15
[Table view] Category:TEXT-LICENSE APPLICATIONS & PERMITS
MONTHYEARL-99-033, Application for Amends to Licenses NPF-2 & NPF-8,to Change TS Re Control Room,Penetration Room & Containment Purge Filtration Sys & Radiation Monitoring Instrumentation,Which Reflect Agreements Reached in 990909 & 16 Discussions1999-10-0404 October 1999 Application for Amends to Licenses NPF-2 & NPF-8,to Change TS Re Control Room,Penetration Room & Containment Purge Filtration Sys & Radiation Monitoring Instrumentation,Which Reflect Agreements Reached in 990909 & 16 Discussions ML20212C5831999-09-15015 September 1999 Application for Amends to Licenses NPF-2 & NPF-8,committing Util to Transfer Certain CTS Requirements Into Util Controlled Documents & Specifying Schedule for Performing New & Revised ITS Surveillances.Revised License Pages,Encl ML20210R5181999-08-12012 August 1999 Revised Page 6 to 990430 LAR to Operate Farley Nuclear Plant,Unit 1,for Cycle 16,based on risk-informed Approach for Evaluation of SG Tube Structural Integrity.Marked Page of Current License,Included L-99-018, Application for Amend to License NPF-2 for Approval to Operate Unit 1,cycle 16 Only,Based on risk-informed Approach for Evaluation of SG Tube Structural Integrity1999-04-30030 April 1999 Application for Amend to License NPF-2 for Approval to Operate Unit 1,cycle 16 Only,Based on risk-informed Approach for Evaluation of SG Tube Structural Integrity L-99-013, Application for Amends to Licenses NPF-2 & NPF-8.Amends Would Increase Dei Limit from 0.15 to 0.3 Uci/Gram IAW 10CFR50.90.Marked-up & Revised Current TS Encl1999-04-0202 April 1999 Application for Amends to Licenses NPF-2 & NPF-8.Amends Would Increase Dei Limit from 0.15 to 0.3 Uci/Gram IAW 10CFR50.90.Marked-up & Revised Current TS Encl ML20155J4391998-11-0606 November 1998 Application for Amends to Licenses NPF-2 & NPF-8,requesting Change to TS Nuclear Instrumentation Sys Power Range Daily Surveillance Requirement ML20154K2451998-10-12012 October 1998 Application for Amends to Licenses NPF-2 & NPF-8,revising Section 6 of TS by Recognizing Addl Mgt Positions Associated with SG Replacement Project & Providing Ability to Approve Procedures Re Project Which May Affect Nuclear Safety ML20216F7051998-03-12012 March 1998 Application for Amends to Licenses NPF-2 & NPF-8 to Revise Existing TS in Entirety.Amend Consists Primarily of Conversion of Current TS to Improved Ts,Per NUREG-1431,rev 1.Vols 1-10 Contain Listed Attachments ML20198H3561998-01-0707 January 1998 Application for Amends to Licenses NPF-2 & NPF-8,adding Note to TS to Specifically Indicate Normal or Emergency Power Supply May Be Inoperable in Modes 5 or 6 Provided That Requirements of TS 3.8.1.2 Are Satisified ML20198E6531997-12-31031 December 1997 Application for Amends to Licenses NPF-2 & NPF-8,changing Nis IR Neutron Flux Reactor Trip Setpoint & Allowable Value to Be Consistent W/W Std TS,NUREG-1431,Rev 1.Proprietary Safety Analysis,Encl.Proprietary Info Withheld ML20198E2891997-12-30030 December 1997 Application for Amends to Licenses NPF-2 & NPF-8,changing Requirements for Auxiliary Bldg & Svc Water Bldg Batteries, Per NRC Staff Concerns as Described in URI 50-348/97-201 & 50-364/97-201 & NOV 50-348/97-11 & 50-364/97-11 ML20198R5181997-10-29029 October 1997 Amends 132 & 124 to Licenses NPF-02 & NPF-08,respectively, Changing TS 3/4.4.9, Specific Activity & Associated Bases to Reduce Limit Associated W/Dose Equivalent iodine-131 ML20211P5811997-10-16016 October 1997 Application for Amends to Licenses NPF-2 & NPF-8,revising Number of Allowable Charging Pumps Capable of Injecting in RCS When Temperature of One or More of RCS Cold Leg Temperatures Is Less than 180 F ML20211A6811997-09-17017 September 1997 Application for Amends to Licenses NPF-2 & NPF-8,amending Primary Coolant Specific Activity,Per GL 95-05 ML20216C9231997-09-0303 September 1997 Application for Amend to License NPF-2,allowing Reduction in Available Paths to Min of 50% w/3 Per Core Quadrant. Non-proprietary & Proprietary W Repts CAA-97-234 & CAA-97-235,encl.Proprietary Info,Withheld ML20149K0971997-07-23023 July 1997 Application for Amends to Licenses NPF-2 & NPF-8,relocating RCS P/T Limits from TS to Proposed PT Limits Rept IAW Guidance Provided by GL 96-03, Relocation of P/T Limit Curves & LTOP Protection Sys Limits ML20148R7351997-06-30030 June 1997 Application for Amends to Licenses NPF-2 & NPF-8, Incorporating Requirements Necessary to Change Basis for Prevention of Criticality in Fuel Storage Pool.Change Eliminates Credit for Boraflex as Neutron Absorbing Matl ML20148Q0981997-06-30030 June 1997 Application for Amends to Licenses NPF-2 & NPF-8,revising & Clarifying Requirements for CR Emergency & Penetration Room Filtration Sys & Related Storage Pool Ventilation Sys & Revises Radiation Monitoring Instrumentation Channels ML20148K7421997-06-13013 June 1997 Application for Amends to Licenses NPF-2 & NPF-8,proposing Changes Found in Tech Specs 3/4.9.13, Storage Pool Ventilation (Fuel Movement) ML20140A3861997-05-28028 May 1997 Application for Amends to Licenses NPF-2 & NPF-8,clarifying That Testing of Each Shared EDG to Comply W/Sr 4.8.1.1.2.e Is Only Required Once Per Five Years on a Per EDG Basis,Not on Per Unit Basis ML20148E5851997-05-27027 May 1997 Application for Amends to Licenses NPF-2 & NPF-8,revising Applicable Modes for Source Range Nuclear Instrumentation & Providing Allowances for an Exception to Requirements for State of Power Supplies for RHR Discharge to Pump Valves ML20138B9161997-04-23023 April 1997 Application for Amends to Licenses NPF-2 & NPF-8,revising Proposed TS Pages to Include Footnote Concerning Filter Pressure Drop Testing & Mechanical Heater Testing ML20137H6011997-03-25025 March 1997 Application for Amend to License NPF-2,requesting Implementation of voltage-based Alternate Repair Criteria, Per GL 95-05 ML20137E2891997-03-24024 March 1997 Amends 125 & 119 to Licenses NPF-2 & NPF-8,respectively, Revising TS to Incorporate Latest Revised Topical Repts Governing Installation of Laser Welded SG Tube Sleeves ML20136F8141997-03-0707 March 1997 Application for Amends to Licenses NPF-2 & NPF-8,revising TS 3/4.6.3 Re Containment Isolation Valves Surveillance Requirements ML20135C6511997-02-24024 February 1997 Application for Amends to Licenses NPF-2 & NPF-8,requesting Revision & Clarification to Surveillance Requirements for Control Room Emergency Filtration Sys,Penetration Room Filtration Sys & Containment Purge Exhaust Filter ML20135C8311997-02-14014 February 1997 Application for Amends to Licenses NPF-2 & NPF-8,revising Specified Max Power Level & Definition of Rated Thermal Power ML20138G9451996-12-26026 December 1996 Application for Amends to Licenses NPF-2 & NPF-8,reflecting Guidance in GL 95-05, SG Tube Support Plate Voltage-Based Repair..., to Use Revised Accident Leakage Limit of 20 Gpm & Include 50% of Rpc Ndds in Calculation.W/O Unit 2 TSs ML20134K5501996-11-15015 November 1996 Application for Amends to Licenses NPF-2 & NPF-8,requesting Deletion of TS 3.6.2.2 Re Containment Spray Additive Sys ML20128F8681996-09-30030 September 1996 Application for Amends to Licenses NPF-2 & NPF-8,relocating cycle-specific Core Operating Parameter Limits to Colr. Proposed Changes Based on Guidance Found in NRC GL 88-16, WOG-90-016,NUREG-1431 & VEGP COLR Approved by NRC ML20117G2911996-08-30030 August 1996 Application for Amend to License NPF-8,requesting Deletion of References to Cycle Specific L* Criteria ML20117D2201996-08-23023 August 1996 Application for Amends to Licenses NPF-2 & NPF-8,requesting to Allow Use of Elevated Sleeve ML20113B6931996-06-24024 June 1996 Application for Amends to Licenses NPF-2 & NPF-8,deleting Requirement for Surveillance of Manual SI Input to Reactor Trip Circuitry Until Next Unit Shutdown ML20113A7991996-06-20020 June 1996 Application to Revise Ts,Reflecting Implementation of 10CFR50,App J,Option B & Represent Crossed Beneficial Licensee Actions ML20112G9711996-06-12012 June 1996 Application for Amends to Licenses NPF-2 & NPF-8,providing Improved Operating Margins as Well as Increased Flexibility W/Respect to Core Designs & Plant Operating Strategy. Rev 2 to NSD-NT-OPL-96-152 Withheld ML20107J9551996-04-23023 April 1996 Application for Amend to License NPF-8,requesting Unit 2 Cycle 11 TS Change for SG Tubes Remaining in Svc ML20107J1521996-04-22022 April 1996 Application for Amend to License NPF-8,reflecting Implementation of New F* Criteria Based on Maintaining Existing Safety Margins for SG Tube Structural Integrity Concurrent W/Allowance for NDE Eddy Current Uncertainty ML20101L9041996-03-29029 March 1996 Application for Amend to License NPF-8,revising TS 3/4.4.6, Steam Generators & Associated Bases,Reflecting Guidance in GL 95-05.Responses to GL & Revised TS Encl ML20095L0161995-12-19019 December 1995 Application for Amends to Licenses NPF-2 & NPF-8,revising Tech Specs Section 3/.7.7 Re Control Room Emergency Ventilation Sys ML20098B0911995-09-26026 September 1995 Application for Amends to Licenses NPF-2 & NPF-8,changing TS 4.6.1.3 to Incorporate Improvements to Containment Air Lock Testing Ref in Chapter 3.6,containment Sys of NUREG-1431, Sts,Westinghouse Plants ML20092F3821995-09-15015 September 1995 Application for Amend to License NPF-2 & NPF-8,eliminating Periodic Pressure Sensor Response Time Testing Requirements ML20084P4901995-05-31031 May 1995 Application for Amends to Licenses NPF-2 & NPF-8,revising TS Associated W/Steam Generator Tube Support Plate voltage- Based Repair Criteria ML20080R8201995-03-0606 March 1995 Application for Amends to Licenses NPF-2 & NPF-8,relocating Seismic & Meteorological Monitoring Instrumentation TSs to FSAR ML20078P8331995-02-14014 February 1995 Application for Amend to Licenses NPF-2 & NPF-8 Re Permanent voltage-based Repair Criteria for Outside Diameter Stress Corrosion Cracking at SG Tube Support Plates for Both Units at Plant ML20077R4071995-01-0909 January 1995 Application for Amends to Licenses NPF-2 & NPF-8, Incorporating line-item TS Improvements to Reduce Surveillance Requirements for Testing During Power Operation in Response to GL 93-05 ML20078S7531994-12-19019 December 1994 Application for Amends to Licenses NPF-2 & NPF-8,revising TS Pages for Mssv,Per NRC Information Notice 94-060, Potential Overpressurization of Main Steam Sys ML20077E3461994-12-0707 December 1994 Application for Amends to Licenses NPF-2 & NPF-8,revising TS to Reflect Guidance in Draft GL 94-XX, Voltage-Based Repair Criteria for Repair of Westinghouse SG Tubes Affected by Outside Diameter Stress Corrosion Cracking ML20078B5451994-10-20020 October 1994 Application for Amends to Licenses NPF-2 & NPF-8,proposing TS 3/4.3.3.6 & Associated Bases,Which Will Delete Requirements for Chlorine Detection Sys from Units 1 & 2 TS ML20072F3401994-08-17017 August 1994 Application for Amends to Licenses NPF-2 & NPF-8,eliminating Periodic Pressure Sensor Response Time Testing Requirements. Rev 1 to WCAP-13787 & Proprietary Rev 1 to WCAP-13632, Elimination of Pressure... encl.WCAP-13632,Rev 1 Withheld ML20070A1001994-06-17017 June 1994 Application for Amend to License NPF-2,revising TS 3/4.2.3 to Increase Nuclear Enthalpy Rise Hot Channel Factor Limit from 1.65 to 1.70 for Vantage 5 Fuel,In Order to Provide Greater Flexibility in Farley Unit 1 Core Design 1999-09-15
[Table view] |
Text
- - - - - _ - _ - - _ .
?
- Aalling Asleimes
[?-v a ;
~
,: / Alibim3 Power Company
- 000 North 18th Street
- - Post Office Box 2641 Rirmingham, Alabama 35291
, Telephone 205 783-6081 F. L. Clayton, Jr.
CLL'Ofo*"' AlabamaPower January 27,'1984 Docket Nos. 50-348 M' 50-354
. Diractor : Nuclear Reactor Regulation U. $. Nuclear Regulatory Commission
. Washington, D.C. 20555 Attention: Mr. S. A. Varga LJoseph M. Farley Nuclear Plant - Units 1 and 2 Proposed Technical Specification Change to D.C. Distribution System Requiremsats~
. Gentlemen:
Alabama Power Company letter dated May 3,1983 proposed changes to the technical specifications regarding the Auxiliary and Service Water Building D.C. . Distribution Systems. Subsequent discussions with the NRC Staff identified the need for submittal of additional information and revision to the-May 3,:1983 proposed changes as contained herein.
Float Voltage Surveillance Requirement Alabama Power Company proposed to revise the existing float voltage surveillance requirement from a single criterion of 2.02 volts to Category B allowable of 2.02. volts and Category A and B limits of 2.07 volts. The NRC Staff indicated that the 2.02 volt value was acceptable based on previous licensing action by the NRC; however, the 2.07 volt limits were unacceptable based on the Standard Technical Specification guidance that 2.13 volt limits
--were required. As discussed with the NRC Staff, Alabama Power Company hereby revises the proposed Category A and B limits to 2.02 volts in
.accordance'with previously approved surveillance requirements for the Farley Nuclear Plant. Attachment 1 provides a revised Table 4.8-2 for each unit.
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. ..' J.t. ftr. S. A. Varga January 27, 1984
.h& U. S. Nuclear Regulatory Commission Page 2 y
. ; . - m. yc NN f.h. . .,N; EA Connector Resistance for Service Water Building Batteries
.- @ Q Y j,h ' Alabama Power Company proposed to verify the Service Water Building 7 y; J ? battery system connector resistance based on a 1500 microhm criterion. The 'Q
- i.i$ NRC Staff requested more information regarding selection of this criterion $
..T.' based on the Standard Technical Specification criterion of 150 microhms for %
resistance testing. %
'f fc.N _4y Alabama Power Company agrees that the Standard Technical Specification
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.r. f 1 criterion (150 microhms) is appropriate for large amperage D.C. distribution +
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t systems such as the Auxiliary Building D.C. Distribution System (i.e., 920 <j
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amp design load) and has proposed to use the 150 microhm guidance for such 2 large amperage systems. However, the Service Water Building D.C. 4 f:M S .g ' Distribution System is a relatively low amperage system designed for an -
- f. 7 accident load of 25 amps for 0.1 second and 1 amp for the next 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />. 4 W. There are 18 connectors (i.e., braided cable connectors) in the Service 9
$.j '.' Water Building battery design such that the proposed 1500 microhm resistance criterion would represent less than 0.8 maximum allowable voltage drop due 11
' .? N to connection resistance at the transient load of 25 amps. This voltage T
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(.5% drop is insignificant when compared with the system nominal 125 volts. % t4
,9 + 4 Also, this maximum allowable voltage drop would be less than the maximum
.k.; .5.Q allowable voltage drop in the Auxiliary Building D.C. Distribution System based on the 150 microhm criterion (i.e.,150 microhms, 59 connectors and 7
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, .g 3 V Q.. 920 amps yields greater than an 8.0 volt drop).
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?:. The relatively low amperage Service Water Building D.C. Distribution (
. h j System utilizes braided cable battery connectors such that the inherent p l
- . u.O resistance is higher than for copper bar type connectors used on the i Auxiliary Building D.C. systems. The 1500 microhm criterion is based on W Q}*.
Au*f assuring that the braided cable connectors have not deteriorated, the
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% $. '. voltage drop is minimal and the connectors are not subjected to a surveillance criterion that would cause ur.necessary cable replacement or a Qvi .5
.f.h system design change.
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- h'.k Auxiliary Building D.C. Distribution Limits During Shutdown
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. 1.E : Alabama Power Company proposed to adopt the wording of the Standard gi Technical Specifications for the Auxiliary Building D.C. Distribution System p[
yg.Q during shutdown except for the requirement to vent the Reactor Coolant q e* System (RCS) within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> should the D.C. system become inoperable. Based %
Y.d; N on discussions with the representatives of Westinghouse, the basis for the D
- i. M9s Standard Technical Specification requirement to vent the RCS is that the ?-
- M generic design for reactor vessel low temperature overpressure protection j
!. ' T depends on the D.C. distribution system. However, the Farley Nuclear Plant %'
..7 low temperature overpressure protection system does not rely on the D.C. t u Z.. distribution system since spring-loaded mechanical relief valves are ~ f.
p%.T .:$(} utilized. The NRC approved the Farley Nuclear Plant low temperature overpressure protection system and associated technical specifications per S
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.. tf.
NUREG-0117, Supplement No. 4, " Safety Evaluation Report related to the operation of Joseph M. Farley Nuclear Plant."
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Mr. S. A. Varga January 27, 1984 Page 3
'U. S. Nuclear Regulatory Commission Since the Farley Nuclear Plant reactor vessel low temperature overpressure protection system differs from the design assumed in the
' Standard Technical Specifications in that it does not rely upon the D.C.
distribution system,- the proposed deviation from the Standard Technical Specification guidance is technically justified. The existing technical specification on the low temperature overpressure protection system (i.e.,
. 3/4.4.1.4) provides the .needed assurance of. proper system operation.
Another area of deviation from the Standard Technical Specification regarding the Auxiliary Building D.C. Distribution System during shutdown is that the May 3,1983 submittal combined the ACTION statement for the battery
. bank, D.C. bus and charger into one statement. In accordance with discussions with the NRC Staff, Alabama Power Company hereby revises the proposed submittal to separate the ACTION statement into two statements, one on the battery bank and D.C. bus and the other on the charger. The revised
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g proposed submittal is, .therefore, in accordance with the Standard Technical Specification guidance. Attachment 2 is a revised Action Statement for J Specification 3.8.2.4 for each unit.
Conclusion The D.C. Distribution System proposed technical specification change, including this supplement, is considered to not involve a Significant Hazards Consideration as defined in 10CFR50.92. These changes are similar to example (ii) of " Examples of Amendments That Are Considered Not Likely to Involve Significant Hazards Considerations" listed in 48FR14870 dated April 6,1983 in that these changes involve restriction and control not presently included in the technical specifications. In addition, the proposed technical specification change conforms in general with the fomat of the
- most recent Westinghouse Standard Technical Specifications (WSTS). The
. differences between the currently approved WSTS and the proposed technical specification change are detailed in' Attachment 1 of the May 3,1983 letter and this supplement. The class of this proposed change was designated as
. Class III' for Unit 1 and Class I for Unit 2 in accordance with 10CFR170.22 requirements. :A check for $4,400 to cover the total amount of fees required was enclosed with the May 3,1983 letter. As noted by the distribution, a copy of this . supplemental letter is being sent to the Alabama State Designee in'accordance with 10CFR50.91 (b)(1).
Yours very tru , ,
/ s
.QL Cl ayton, Jr. /
FLCJ r/GGY:grs-D1 g Attachments cc: See Page 4
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Mr. S. A. Varga January 27, 1984 U. S. Nuclear Regulatory Comission Page 4 cc: Mr. R. A. Thomas Mr. G. F. Trowbridge Mr. J. P. O'P.eilly Mr. E. A. Reeves Mr. W. H. Bradford Dr. I. L. Myers
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