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Category:OPERATING LICENSES-APPLIATION TO AMEND-RENEW EXISTING
MONTHYEARNRC-99-0082, Application for Amend to License NPF-43,revising TS 3/4.6.1.8 to Allow Continued Operation Until Next Plant Shutdown at Which Time Valve T4803F601 Will Be Repaired1999-09-24024 September 1999 Application for Amend to License NPF-43,revising TS 3/4.6.1.8 to Allow Continued Operation Until Next Plant Shutdown at Which Time Valve T4803F601 Will Be Repaired NRC-99-0072, Application for Amend to License NPF-43,revising SRs & Bases for Div I Battery Sys to Agree with Design of New Battery Replacement1999-09-10010 September 1999 Application for Amend to License NPF-43,revising SRs & Bases for Div I Battery Sys to Agree with Design of New Battery Replacement NRC-99-0078, Rev 14 to Application for Amend to License NPF-43,providing Update for Remaining Open Issues Associated with NRC Review of ITS Submittal.Brief Abstract of Changes Included in Rev & Revised Pages for Submittal & Rev Instructions,Included1999-08-25025 August 1999 Rev 14 to Application for Amend to License NPF-43,providing Update for Remaining Open Issues Associated with NRC Review of ITS Submittal.Brief Abstract of Changes Included in Rev & Revised Pages for Submittal & Rev Instructions,Included NRC-99-0048, Application for Amend to License NPF-43 to Change TS to Include Provisions for Enabling Oscillation Power Range Monitor (OPRM) Upscale Function in Average Power Range Monitor (Aprm).Draft TS Pages Encl1999-07-30030 July 1999 Application for Amend to License NPF-43 to Change TS to Include Provisions for Enabling Oscillation Power Range Monitor (OPRM) Upscale Function in Average Power Range Monitor (Aprm).Draft TS Pages Encl NRC-99-0035, Application for Amend to License DPR-9 to Modify TS Section D.3.Amend Would Eliminate TS Surveillance Requirement for Ni Cover Gas on Nearly Empty Primary Sodium Storage Tanks in Sodium Bldg Complex.With marked-up & Typed TS Pages1999-04-20020 April 1999 Application for Amend to License DPR-9 to Modify TS Section D.3.Amend Would Eliminate TS Surveillance Requirement for Ni Cover Gas on Nearly Empty Primary Sodium Storage Tanks in Sodium Bldg Complex.With marked-up & Typed TS Pages NRC-99-0025, Application for Amend to License NPF-43,modifying TS SR 4.4.1.1.1 to Require Each Recirculation Pump Discharge Valve Be Demonstrated Operable at Least Once Every 18 Months & Deleting Footnote That Applies to TS 4.4.1.1.11999-03-23023 March 1999 Application for Amend to License NPF-43,modifying TS SR 4.4.1.1.1 to Require Each Recirculation Pump Discharge Valve Be Demonstrated Operable at Least Once Every 18 Months & Deleting Footnote That Applies to TS 4.4.1.1.1 NRC-98-0122, Rev 1 to 980403 Application for Amend to License NPF-43, Proposing TS Change for Conversion to Improved Standard Ts. Revised Pages for Submittal & Brief Abstract of Changes, Encl1998-09-28028 September 1998 Rev 1 to 980403 Application for Amend to License NPF-43, Proposing TS Change for Conversion to Improved Standard Ts. Revised Pages for Submittal & Brief Abstract of Changes, Encl NRC-98-0128, Rev to 980128 Application for Amend to License DPR-9, Revising TS to Implement Provisions of 1996 Decommissioning Rule,Including Requirements for Control of Effluents,Dose Limits & Annual Reporting of 10CFR50.36a1998-08-26026 August 1998 Rev to 980128 Application for Amend to License DPR-9, Revising TS to Implement Provisions of 1996 Decommissioning Rule,Including Requirements for Control of Effluents,Dose Limits & Annual Reporting of 10CFR50.36a NRC-98-0117, Application for Amend to License NPF-43,revising Table 4.0.2-1 to Include Two Functional Units for TS 4.3.1.3 (RPS Response Time Testing) & Allowing one-time Extension of Respective Surveillance Intervals1998-07-23023 July 1998 Application for Amend to License NPF-43,revising Table 4.0.2-1 to Include Two Functional Units for TS 4.3.1.3 (RPS Response Time Testing) & Allowing one-time Extension of Respective Surveillance Intervals NRC-98-0044, Application for Amend to License DPR-9,allowing Util to Possess Special Nuclear Matl in Quantity Totaling No More than 15 Grams of U-235,U-233 or Pu,Or Any Combination Thereof,W/Pu Activity Totaling No More than 2 Ci1998-07-17017 July 1998 Application for Amend to License DPR-9,allowing Util to Possess Special Nuclear Matl in Quantity Totaling No More than 15 Grams of U-235,U-233 or Pu,Or Any Combination Thereof,W/Pu Activity Totaling No More than 2 Ci NRC-98-0040, Application for Amend to License NPF-43,requesting to Allow one-time Extension of Surveillance Intervals to Delay Shutdown for Upcoming Sixth Refueling Outage (RFO6) Until 9809041998-06-26026 June 1998 Application for Amend to License NPF-43,requesting to Allow one-time Extension of Surveillance Intervals to Delay Shutdown for Upcoming Sixth Refueling Outage (RFO6) Until 980904 ML20248L7981998-06-0505 June 1998 Application for Amend to License NPF-43,revising TS Section 2.1.2.Proprietary & non-proprietary Info,Encl.Proprietary Info Withheld NRC-98-0065, Application for Amend to License NPF-43,to Add Configuration Risk Mgt Program to TS Section 6.8.5,contingent on Approval of Previously Submitted License Amend for TS 3.8.1.11998-04-27027 April 1998 Application for Amend to License NPF-43,to Add Configuration Risk Mgt Program to TS Section 6.8.5,contingent on Approval of Previously Submitted License Amend for TS 3.8.1.1 NRC-98-0071, Application for Amend to License NPF-43,proposing Align Shutdown Action Statements for Primary Containment Oxygen Monitoring Instrumentation in Three Specifications1998-04-0909 April 1998 Application for Amend to License NPF-43,proposing Align Shutdown Action Statements for Primary Containment Oxygen Monitoring Instrumentation in Three Specifications NRC-98-0043, Application for Amend to License NPF-43 to Convert Current TS to Improved Ts.Meeting Is Requested to Discuss Review Schedule & Contents of Amend.Vol 1 Includes Application & Justification.Vols 2-13 Contain Improved TS1998-04-0303 April 1998 Application for Amend to License NPF-43 to Convert Current TS to Improved Ts.Meeting Is Requested to Discuss Review Schedule & Contents of Amend.Vol 1 Includes Application & Justification.Vols 2-13 Contain Improved TS NRC-98-0057, Application for Amend to License NPF-43,revising Requirements Associated W/Containment Oxygen & Hydrogen Monitors1998-04-0202 April 1998 Application for Amend to License NPF-43,revising Requirements Associated W/Containment Oxygen & Hydrogen Monitors NRC-98-0062, Application for Amend to License NPF-43,modifying Drywell Oxygen Monitoring Instrumentation Action Requirements to Be Consistent W/Those Contained in NUREG-1433,Rev 1, STS GE Plants,BWR/41998-04-0202 April 1998 Application for Amend to License NPF-43,modifying Drywell Oxygen Monitoring Instrumentation Action Requirements to Be Consistent W/Those Contained in NUREG-1433,Rev 1, STS GE Plants,BWR/4 NRC-98-0034, Application for Amend to License NPF-43,revising Footnote Specifying Conditions Where Isolation Valves Associated W/ LPCI Sys Operation Are Repositioned1998-03-27027 March 1998 Application for Amend to License NPF-43,revising Footnote Specifying Conditions Where Isolation Valves Associated W/ LPCI Sys Operation Are Repositioned NRC-98-0033, Application for Amend to License NPF-43,eliminating Incorrect Descriptive Info Re Water Inventory in CST Reserved for Hpci/Rcic & Raising CST Min Water Level for Core Spray1998-03-27027 March 1998 Application for Amend to License NPF-43,eliminating Incorrect Descriptive Info Re Water Inventory in CST Reserved for Hpci/Rcic & Raising CST Min Water Level for Core Spray NRC-98-0002, Application for Amend to License NPF-43,revising SRs for Div II Battery Sys to Agree W/Design of New Battery Replacement1998-01-28028 January 1998 Application for Amend to License NPF-43,revising SRs for Div II Battery Sys to Agree W/Design of New Battery Replacement NRC-98-0027, Application for Amend to License DPR-6,modifying Sections F & I of Plant TS to Include Requirements for Control of Effluents,Dose Limits & Annual Reporting Per 10CFR50.36a1998-01-28028 January 1998 Application for Amend to License DPR-6,modifying Sections F & I of Plant TS to Include Requirements for Control of Effluents,Dose Limits & Annual Reporting Per 10CFR50.36a NRC-98-0006, Application for Amend to License NPF-43,changing Surveillance Interval in TS 4.4.3.2.2.a by Extending It from Current 18 Month Testing Interval to 24 Month Testing Interval to Be Consistent W/Asme Code Requirements1998-01-28028 January 1998 Application for Amend to License NPF-43,changing Surveillance Interval in TS 4.4.3.2.2.a by Extending It from Current 18 Month Testing Interval to 24 Month Testing Interval to Be Consistent W/Asme Code Requirements NRC-98-0008, Application for Amend to License NPF-43,revising Footnotes Specifying Conditions Under Which SRs Associated W/Ts 3/4.9.1, Reactor Mode Switch, Can Be Performed1998-01-28028 January 1998 Application for Amend to License NPF-43,revising Footnotes Specifying Conditions Under Which SRs Associated W/Ts 3/4.9.1, Reactor Mode Switch, Can Be Performed NRC-98-0003, Application for Amend to License NPF-43,revising Tech Specs to Improve Administrative Controls Re thermal-hydraulic Stability & Idle Recirculation Loop Startup & Eliminating Neutron Flux Indication from TS1998-01-28028 January 1998 Application for Amend to License NPF-43,revising Tech Specs to Improve Administrative Controls Re thermal-hydraulic Stability & Idle Recirculation Loop Startup & Eliminating Neutron Flux Indication from TS NRC-98-0023, Application for Amend to License DPR-9,allowing Util to Possess Contaminated Apparatus & Equipment & Radioactive Sources at Fermi 1 Containing Byproduct Matl Not Produced by Operation of Plant Reactor1998-01-28028 January 1998 Application for Amend to License DPR-9,allowing Util to Possess Contaminated Apparatus & Equipment & Radioactive Sources at Fermi 1 Containing Byproduct Matl Not Produced by Operation of Plant Reactor NRC-98-0025, Application for Amend to License DPR-9,changing TS on Access Control to Provide Flexibility While Maintaining Similar Controls Over Access1998-01-28028 January 1998 Application for Amend to License DPR-9,changing TS on Access Control to Provide Flexibility While Maintaining Similar Controls Over Access NRC-97-0115, Application for Amend to License DPR-9,modifying Part 2.A in Order to Delete Reference to Six Letters Now Listed & Instead Refer to Encl Fermi 1 SAR1997-12-15015 December 1997 Application for Amend to License DPR-9,modifying Part 2.A in Order to Delete Reference to Six Letters Now Listed & Instead Refer to Encl Fermi 1 SAR NRC-97-0105, Application for Amend to License NPF-43,revising TS to Be Consistent W/Planned Replacement of Current Power Range Monitoring Portion of Existing Nms1997-12-10010 December 1997 Application for Amend to License NPF-43,revising TS to Be Consistent W/Planned Replacement of Current Power Range Monitoring Portion of Existing Nms ML20211J1971997-09-29029 September 1997 Application for Amend to License NPF-43,relocating Selected Requirements & Associated Bases from TS to Ufsar.Rev of TS Index & List of Tables to Reflect Relocation Requested NRC-97-0107, Application for Amend to License NPF-43,adding Special Test Exception to Allow Unit to Remain in Operational Condition 4 W/Reactor Coolant Temps Greater than 200 F,But Less than 212 F,When Performing Inservice Leak & Hydrostatic Testing1997-09-0505 September 1997 Application for Amend to License NPF-43,adding Special Test Exception to Allow Unit to Remain in Operational Condition 4 W/Reactor Coolant Temps Greater than 200 F,But Less than 212 F,When Performing Inservice Leak & Hydrostatic Testing NRC-97-0037, Application for Amend to License NPF-43,relocating Surveillance Requirements for Reactor Recirculation Sys MG Set Scoop Tube Stop Setpoints to UFSAR1997-06-20020 June 1997 Application for Amend to License NPF-43,relocating Surveillance Requirements for Reactor Recirculation Sys MG Set Scoop Tube Stop Setpoints to UFSAR NRC-97-0031, Application for Amend to License NPF-43,requesting Elimination of Selected Response Time Testing Requirements1997-03-27027 March 1997 Application for Amend to License NPF-43,requesting Elimination of Selected Response Time Testing Requirements NRC-96-0134, Application for Amend to License NPF-43,modifying TS Section 3.1.4.3,Table 3.3.6-1 & Table 4.3.6-1 Re Rod Block Monitor Applicability1996-12-0202 December 1996 Application for Amend to License NPF-43,modifying TS Section 3.1.4.3,Table 3.3.6-1 & Table 4.3.6-1 Re Rod Block Monitor Applicability ML20129F0611996-09-25025 September 1996 Application for Amend to License NPF-43,revising Tech Spec 4.8.4.3 Re Periodic Testing Requirement for Thermal Overload Protection Devices NRC-96-0075, Application for Amend to License NPF-43,changing SLMCPRs in TS 2.1.2 to Reflect Results of cycle-specific Calculation Performed for Plant Operating Cycle 6 Expected to Commence in 1996 & Deleting Specific SLMCPR Value1996-09-0505 September 1996 Application for Amend to License NPF-43,changing SLMCPRs in TS 2.1.2 to Reflect Results of cycle-specific Calculation Performed for Plant Operating Cycle 6 Expected to Commence in 1996 & Deleting Specific SLMCPR Value NRC-96-0003, Application for Amend to License NPF-43,modifying Charcoal Testing Stds for Control Room Emergency Filtration Sys & Standby Gas Treatment Sys1996-03-25025 March 1996 Application for Amend to License NPF-43,modifying Charcoal Testing Stds for Control Room Emergency Filtration Sys & Standby Gas Treatment Sys ML20095K4211995-12-21021 December 1995 Application for Amend to License NPF-43,incorporating 10CFR50,App J,Option B NRC-95-0124, Application for Amend to License NPF-43,modifying TS Action Statements 3.8.1.1.b & 3.8.1.1.d,SRs 4.8.1.1.2.a,4.8.1.1.3 & 4.8.1.2,Table 4.8.1.1.2-1 & Bases 3/4.8.1,3/4.8.2 & 3/4.8.31995-11-22022 November 1995 Application for Amend to License NPF-43,modifying TS Action Statements 3.8.1.1.b & 3.8.1.1.d,SRs 4.8.1.1.2.a,4.8.1.1.3 & 4.8.1.2,Table 4.8.1.1.2-1 & Bases 3/4.8.1,3/4.8.2 & 3/4.8.3 NRC-95-0104, Application for Amend to License NPF-43,incorporating one- Time Deferral of Limited Aspects of SR 4.3.3.2,4.8.1.1.2.e. 4.b & 4.8.1.1.2.e.6.b Into Plant TS1995-10-0202 October 1995 Application for Amend to License NPF-43,incorporating one- Time Deferral of Limited Aspects of SR 4.3.3.2,4.8.1.1.2.e. 4.b & 4.8.1.1.2.e.6.b Into Plant TS NRC-95-0096, Application for Amend to License NPF-43,revising TS Re Sys Testing,Instrumentation Calibr,Component Insp,Component Testing,Response Time Testing & Logic Sys Functional Tests to Allow one-time Extension of Surveillance Intervals1995-09-20020 September 1995 Application for Amend to License NPF-43,revising TS Re Sys Testing,Instrumentation Calibr,Component Insp,Component Testing,Response Time Testing & Logic Sys Functional Tests to Allow one-time Extension of Surveillance Intervals NRC-94-0107, Application for Amend to License NPF-43,proposing Changes to Administrative Controls Section of Ts,Consistent W/Guidance in NUREG-1433 & GL 93-07, Mod of Ts...For Emergency & Security Plans1994-12-15015 December 1994 Application for Amend to License NPF-43,proposing Changes to Administrative Controls Section of Ts,Consistent W/Guidance in NUREG-1433 & GL 93-07, Mod of Ts...For Emergency & Security Plans NRC-94-0047, Application for Amend to License NPF-43,incorporating Changes to Ts,Removing Component Lists from TS Sections 3.6.3 & 3.8.4.3 Per GL 91-081994-05-10010 May 1994 Application for Amend to License NPF-43,incorporating Changes to Ts,Removing Component Lists from TS Sections 3.6.3 & 3.8.4.3 Per GL 91-08 NRC-94-0027, Application for Amend to License NPF-43,relocating Response Time Limit Tables from TS to Ufsar,In Response to GL 93-08 & BWROG Topical Rept NEDO-322911994-04-26026 April 1994 Application for Amend to License NPF-43,relocating Response Time Limit Tables from TS to Ufsar,In Response to GL 93-08 & BWROG Topical Rept NEDO-32291 NRC-93-0151, Application for Amend to License NPF-43 Re Reduced Testing During Power Operation1994-03-29029 March 1994 Application for Amend to License NPF-43 Re Reduced Testing During Power Operation NRC-93-0143, Application for Amend to License DPR-9,revising TS for Implementation of Revised 10CFR20 Requirements1993-12-0909 December 1993 Application for Amend to License DPR-9,revising TS for Implementation of Revised 10CFR20 Requirements NRC-93-0077, Application for Amend to License NPF-43.Amend Provides Updated Lab Testng Standard for Surveillance Testing of Activated Charcoal Samples from Control Room Emergency Filtration Sys1993-07-29029 July 1993 Application for Amend to License NPF-43.Amend Provides Updated Lab Testng Standard for Surveillance Testing of Activated Charcoal Samples from Control Room Emergency Filtration Sys NRC-93-0061, Application for Amend to License NPF-43,revising TS to Extend Instrument Calibr Intervals to 36 Months for Selected Instrumentation,Per BWROG Licensing Topical Rept NEDC-32160P,Dec 1992.GE Proprietary Rept Encl.Rept Withheld1993-07-29029 July 1993 Application for Amend to License NPF-43,revising TS to Extend Instrument Calibr Intervals to 36 Months for Selected Instrumentation,Per BWROG Licensing Topical Rept NEDC-32160P,Dec 1992.GE Proprietary Rept Encl.Rept Withheld NRC-93-0078, Application for Amend to License NPF-43,changing TS 6.8.5.e to Provide Proper Refs to 10CFR20 as Result of New Section Numbers1993-07-29029 July 1993 Application for Amend to License NPF-43,changing TS 6.8.5.e to Provide Proper Refs to 10CFR20 as Result of New Section Numbers NRC-93-0062, Application for Amend to License NPF-43,changing Tech Specs Include Modification to Job Titles Following Mgt Reorganization,Changes to Onsite Review Organization Membership Description & Change to Overtime Requirements1993-05-24024 May 1993 Application for Amend to License NPF-43,changing Tech Specs Include Modification to Job Titles Following Mgt Reorganization,Changes to Onsite Review Organization Membership Description & Change to Overtime Requirements NRC-93-0038, Application for Amend to License NPF-43,modifying Leakage Testing Requirements for Primary Containment Isolation Valves in Injection Flow Paths of LPCI Mode of RHR Sys1993-05-24024 May 1993 Application for Amend to License NPF-43,modifying Leakage Testing Requirements for Primary Containment Isolation Valves in Injection Flow Paths of LPCI Mode of RHR Sys 1999-09-24
[Table view] Category:TEXT-LICENSE APPLICATIONS & PERMITS
MONTHYEARML20217N4301999-10-25025 October 1999 Amend 17 to License DPR-9,revising TS by Deleting SR D.3.c, Which Required Weekly Observation of Nitrogen Cover Gas Pressure within Sodium Storage Tanks Located in Sodium Building ML20217M7051999-10-19019 October 1999 Amend 135 to License NPF-43,revising Current TS 3.6.1.8 by Adding Footnote to Action B.Footnote Allows Continued Operation of Fermi 2 with Leakage of Penetration X-26 Exceeding Limit in TS 4.6.1.8.2 NRC-99-0082, Application for Amend to License NPF-43,revising TS 3/4.6.1.8 to Allow Continued Operation Until Next Plant Shutdown at Which Time Valve T4803F601 Will Be Repaired1999-09-24024 September 1999 Application for Amend to License NPF-43,revising TS 3/4.6.1.8 to Allow Continued Operation Until Next Plant Shutdown at Which Time Valve T4803F601 Will Be Repaired NRC-99-0072, Application for Amend to License NPF-43,revising SRs & Bases for Div I Battery Sys to Agree with Design of New Battery Replacement1999-09-10010 September 1999 Application for Amend to License NPF-43,revising SRs & Bases for Div I Battery Sys to Agree with Design of New Battery Replacement NRC-99-0078, Rev 14 to Application for Amend to License NPF-43,providing Update for Remaining Open Issues Associated with NRC Review of ITS Submittal.Brief Abstract of Changes Included in Rev & Revised Pages for Submittal & Rev Instructions,Included1999-08-25025 August 1999 Rev 14 to Application for Amend to License NPF-43,providing Update for Remaining Open Issues Associated with NRC Review of ITS Submittal.Brief Abstract of Changes Included in Rev & Revised Pages for Submittal & Rev Instructions,Included NRC-99-0048, Application for Amend to License NPF-43 to Change TS to Include Provisions for Enabling Oscillation Power Range Monitor (OPRM) Upscale Function in Average Power Range Monitor (Aprm).Draft TS Pages Encl1999-07-30030 July 1999 Application for Amend to License NPF-43 to Change TS to Include Provisions for Enabling Oscillation Power Range Monitor (OPRM) Upscale Function in Average Power Range Monitor (Aprm).Draft TS Pages Encl ML20207A8841999-05-25025 May 1999 Amend 133 to License NPF-43,revising SR 4.4.1.1.1 to Require Each Recirculation Pump Discharge Valve Be Demonstrated Operable at Least Once Every 18 Months,Deleting * Footnote from SR & Revising Footnote Itself to Read Not Used NRC-99-0035, Application for Amend to License DPR-9 to Modify TS Section D.3.Amend Would Eliminate TS Surveillance Requirement for Ni Cover Gas on Nearly Empty Primary Sodium Storage Tanks in Sodium Bldg Complex.With marked-up & Typed TS Pages1999-04-20020 April 1999 Application for Amend to License DPR-9 to Modify TS Section D.3.Amend Would Eliminate TS Surveillance Requirement for Ni Cover Gas on Nearly Empty Primary Sodium Storage Tanks in Sodium Bldg Complex.With marked-up & Typed TS Pages ML20205Q7091999-04-15015 April 1999 Amend 16 to License DPR-9,allowing Possession of Nominal Amount of Special Nuclear Matl NRC-99-0025, Application for Amend to License NPF-43,modifying TS SR 4.4.1.1.1 to Require Each Recirculation Pump Discharge Valve Be Demonstrated Operable at Least Once Every 18 Months & Deleting Footnote That Applies to TS 4.4.1.1.11999-03-23023 March 1999 Application for Amend to License NPF-43,modifying TS SR 4.4.1.1.1 to Require Each Recirculation Pump Discharge Valve Be Demonstrated Operable at Least Once Every 18 Months & Deleting Footnote That Applies to TS 4.4.1.1.1 ML20207F9811999-03-0303 March 1999 Amend 132 to License NPF-43,revising TS 3.7.1.2, Emergency Equipment Cooling Water Sys, Action a & TS 3.8.1.1, AC Sources - Operating, Action C,To Be Consistent with TS 3.7.1.2 ML20203F8541999-02-0808 February 1999 Amend 131 to License NPF-43,revising TSs 3.5.2 & 3.5.3 & Associated Bases,Raising Min Water Level for Core Spray Sys in Condensate Storage Tank ML20203F8311999-02-0808 February 1999 Amend 130 to License NPF-43,revising TS by Removing Surveillance Requirements 4.4.1.1.2 for Setting Reactor Recirculation Sys MG Set Scoop Tube Stops ML20198S3271999-01-0606 January 1999 Amend 15 to License DPR-9,consisting of Changes to TS ML20154R2251998-10-21021 October 1998 Amend 13 to License DPR-9,allowing Access Control Flexibility,Establishing Compensatory Provisions Re PA Boundary,Eliminating Redundancy Between Ts,Revising Figure B-1 & Correcting Typos NRC-98-0122, Rev 1 to 980403 Application for Amend to License NPF-43, Proposing TS Change for Conversion to Improved Standard Ts. Revised Pages for Submittal & Brief Abstract of Changes, Encl1998-09-28028 September 1998 Rev 1 to 980403 Application for Amend to License NPF-43, Proposing TS Change for Conversion to Improved Standard Ts. Revised Pages for Submittal & Brief Abstract of Changes, Encl ML20154B5341998-09-21021 September 1998 Amend 129 to License NPF-43,revising TS 2.1.2 by Changing Values for Safety Limit Minimum Critical Power Ratio from 1.09 to 1.11 for Two Recirculation Loop Operation & from 1.11 to 1.13 for Single Recirculation Loop Operation NRC-98-0128, Rev to 980128 Application for Amend to License DPR-9, Revising TS to Implement Provisions of 1996 Decommissioning Rule,Including Requirements for Control of Effluents,Dose Limits & Annual Reporting of 10CFR50.36a1998-08-26026 August 1998 Rev to 980128 Application for Amend to License DPR-9, Revising TS to Implement Provisions of 1996 Decommissioning Rule,Including Requirements for Control of Effluents,Dose Limits & Annual Reporting of 10CFR50.36a ML20237E2031998-08-25025 August 1998 Amend 126 to License NPF-43,revises Footnote in TS 3.5.1 & 3.5.2,to Indicate That LPCI Sys Loop May Be Considered Operable During Alignment & Operation for Decay Heat Removal If Capable of Being Manually Realigned ML20237E1711998-08-25025 August 1998 Amend 127 to License NPF-43,revising SR 4.8.4.3 to Clarify Situational Testing Requirement for Thermal Overload Devices to Indicate That This Portion of Requirement Must Be Completed Upon Initial Installation of Thermal Overload ML20237C5531998-08-20020 August 1998 Amend 125 to License NPF-43,revising TS 3.3.7.5 to Permit Entering Operational Conditions 1 & 2 Prior to Completion of SR for Primary Containment H & O Monitors to Establish Conditions Necessary to Properly Perform Calibrations ML20237D1461998-08-0404 August 1998 Amend 124 to License NPF-43,providing one-time Extension of Interval for Number of TS Surveillance Requirements That Will Be Performed During 6th Refueling Outage ML20237D2001998-07-31031 July 1998 Amend 123 to License NPF-43,revising TS 3.4.2.1, Safety Relief Valves, Changing SRV Setpoint Tolerance from Plus/Minus 1% to Plus/Minus 3% NRC-98-0117, Application for Amend to License NPF-43,revising Table 4.0.2-1 to Include Two Functional Units for TS 4.3.1.3 (RPS Response Time Testing) & Allowing one-time Extension of Respective Surveillance Intervals1998-07-23023 July 1998 Application for Amend to License NPF-43,revising Table 4.0.2-1 to Include Two Functional Units for TS 4.3.1.3 (RPS Response Time Testing) & Allowing one-time Extension of Respective Surveillance Intervals NRC-98-0044, Application for Amend to License DPR-9,allowing Util to Possess Special Nuclear Matl in Quantity Totaling No More than 15 Grams of U-235,U-233 or Pu,Or Any Combination Thereof,W/Pu Activity Totaling No More than 2 Ci1998-07-17017 July 1998 Application for Amend to License DPR-9,allowing Util to Possess Special Nuclear Matl in Quantity Totaling No More than 15 Grams of U-235,U-233 or Pu,Or Any Combination Thereof,W/Pu Activity Totaling No More than 2 Ci ML20236R1391998-07-11011 July 1998 Amend 122 to License NPF-43,revising TS for Replacement of Power Range Neutron Monitoring Sys ML20236M7411998-07-0909 July 1998 Amend 121 to License DPR-43,revising TS Surveillance Requirements for Div II 130/260 Volt Dc Battery to Accomodate Design of Replacement Battery NRC-98-0040, Application for Amend to License NPF-43,requesting to Allow one-time Extension of Surveillance Intervals to Delay Shutdown for Upcoming Sixth Refueling Outage (RFO6) Until 9809041998-06-26026 June 1998 Application for Amend to License NPF-43,requesting to Allow one-time Extension of Surveillance Intervals to Delay Shutdown for Upcoming Sixth Refueling Outage (RFO6) Until 980904 ML20248L7981998-06-0505 June 1998 Application for Amend to License NPF-43,revising TS Section 2.1.2.Proprietary & non-proprietary Info,Encl.Proprietary Info Withheld ML20248K9141998-06-0202 June 1998 Amend 119 to License NPF-43,revising TS 3.8.1.1 to Change EDG Allowed Outage Time from 3 to 7 Days & Adds Requirement to Verify That Combustion turbine-general 11-1 Available Prior to Removing an EDG from Svc ML20248F1481998-05-28028 May 1998 Amend 118 to License NPF-43,revises TS SR 4.4.3.2.2.a for Leak Rate Test of Pressure Isolation Valves,Extending from Current 18-month Interval to 24-month Interval NRC-98-0065, Application for Amend to License NPF-43,to Add Configuration Risk Mgt Program to TS Section 6.8.5,contingent on Approval of Previously Submitted License Amend for TS 3.8.1.11998-04-27027 April 1998 Application for Amend to License NPF-43,to Add Configuration Risk Mgt Program to TS Section 6.8.5,contingent on Approval of Previously Submitted License Amend for TS 3.8.1.1 NRC-98-0071, Application for Amend to License NPF-43,proposing Align Shutdown Action Statements for Primary Containment Oxygen Monitoring Instrumentation in Three Specifications1998-04-0909 April 1998 Application for Amend to License NPF-43,proposing Align Shutdown Action Statements for Primary Containment Oxygen Monitoring Instrumentation in Three Specifications NRC-98-0043, Application for Amend to License NPF-43 to Convert Current TS to Improved Ts.Meeting Is Requested to Discuss Review Schedule & Contents of Amend.Vol 1 Includes Application & Justification.Vols 2-13 Contain Improved TS1998-04-0303 April 1998 Application for Amend to License NPF-43 to Convert Current TS to Improved Ts.Meeting Is Requested to Discuss Review Schedule & Contents of Amend.Vol 1 Includes Application & Justification.Vols 2-13 Contain Improved TS NRC-98-0057, Application for Amend to License NPF-43,revising Requirements Associated W/Containment Oxygen & Hydrogen Monitors1998-04-0202 April 1998 Application for Amend to License NPF-43,revising Requirements Associated W/Containment Oxygen & Hydrogen Monitors NRC-98-0062, Application for Amend to License NPF-43,modifying Drywell Oxygen Monitoring Instrumentation Action Requirements to Be Consistent W/Those Contained in NUREG-1433,Rev 1, STS GE Plants,BWR/41998-04-0202 April 1998 Application for Amend to License NPF-43,modifying Drywell Oxygen Monitoring Instrumentation Action Requirements to Be Consistent W/Those Contained in NUREG-1433,Rev 1, STS GE Plants,BWR/4 ML20217M0921998-03-31031 March 1998 Amend 116 to License NPF-43,revising Footnote in TS Table 1.2 & * Footnote Associated W/Surveillance Requirements 4.9.1.2 & 4.9.1.3 to Allow Placing Mode Switch in Run or Startup/Hot Standby Positions NRC-98-0033, Application for Amend to License NPF-43,eliminating Incorrect Descriptive Info Re Water Inventory in CST Reserved for Hpci/Rcic & Raising CST Min Water Level for Core Spray1998-03-27027 March 1998 Application for Amend to License NPF-43,eliminating Incorrect Descriptive Info Re Water Inventory in CST Reserved for Hpci/Rcic & Raising CST Min Water Level for Core Spray NRC-98-0034, Application for Amend to License NPF-43,revising Footnote Specifying Conditions Where Isolation Valves Associated W/ LPCI Sys Operation Are Repositioned1998-03-27027 March 1998 Application for Amend to License NPF-43,revising Footnote Specifying Conditions Where Isolation Valves Associated W/ LPCI Sys Operation Are Repositioned NRC-98-0025, Application for Amend to License DPR-9,changing TS on Access Control to Provide Flexibility While Maintaining Similar Controls Over Access1998-01-28028 January 1998 Application for Amend to License DPR-9,changing TS on Access Control to Provide Flexibility While Maintaining Similar Controls Over Access NRC-98-0027, Application for Amend to License DPR-6,modifying Sections F & I of Plant TS to Include Requirements for Control of Effluents,Dose Limits & Annual Reporting Per 10CFR50.36a1998-01-28028 January 1998 Application for Amend to License DPR-6,modifying Sections F & I of Plant TS to Include Requirements for Control of Effluents,Dose Limits & Annual Reporting Per 10CFR50.36a NRC-98-0003, Application for Amend to License NPF-43,revising Tech Specs to Improve Administrative Controls Re thermal-hydraulic Stability & Idle Recirculation Loop Startup & Eliminating Neutron Flux Indication from TS1998-01-28028 January 1998 Application for Amend to License NPF-43,revising Tech Specs to Improve Administrative Controls Re thermal-hydraulic Stability & Idle Recirculation Loop Startup & Eliminating Neutron Flux Indication from TS NRC-98-0006, Application for Amend to License NPF-43,changing Surveillance Interval in TS 4.4.3.2.2.a by Extending It from Current 18 Month Testing Interval to 24 Month Testing Interval to Be Consistent W/Asme Code Requirements1998-01-28028 January 1998 Application for Amend to License NPF-43,changing Surveillance Interval in TS 4.4.3.2.2.a by Extending It from Current 18 Month Testing Interval to 24 Month Testing Interval to Be Consistent W/Asme Code Requirements NRC-98-0002, Application for Amend to License NPF-43,revising SRs for Div II Battery Sys to Agree W/Design of New Battery Replacement1998-01-28028 January 1998 Application for Amend to License NPF-43,revising SRs for Div II Battery Sys to Agree W/Design of New Battery Replacement NRC-98-0008, Application for Amend to License NPF-43,revising Footnotes Specifying Conditions Under Which SRs Associated W/Ts 3/4.9.1, Reactor Mode Switch, Can Be Performed1998-01-28028 January 1998 Application for Amend to License NPF-43,revising Footnotes Specifying Conditions Under Which SRs Associated W/Ts 3/4.9.1, Reactor Mode Switch, Can Be Performed NRC-98-0023, Application for Amend to License DPR-9,allowing Util to Possess Contaminated Apparatus & Equipment & Radioactive Sources at Fermi 1 Containing Byproduct Matl Not Produced by Operation of Plant Reactor1998-01-28028 January 1998 Application for Amend to License DPR-9,allowing Util to Possess Contaminated Apparatus & Equipment & Radioactive Sources at Fermi 1 Containing Byproduct Matl Not Produced by Operation of Plant Reactor NRC-97-0115, Application for Amend to License DPR-9,modifying Part 2.A in Order to Delete Reference to Six Letters Now Listed & Instead Refer to Encl Fermi 1 SAR1997-12-15015 December 1997 Application for Amend to License DPR-9,modifying Part 2.A in Order to Delete Reference to Six Letters Now Listed & Instead Refer to Encl Fermi 1 SAR NRC-97-0105, Application for Amend to License NPF-43,revising TS to Be Consistent W/Planned Replacement of Current Power Range Monitoring Portion of Existing Nms1997-12-10010 December 1997 Application for Amend to License NPF-43,revising TS to Be Consistent W/Planned Replacement of Current Power Range Monitoring Portion of Existing Nms ML20217E3371997-09-30030 September 1997 Amend 114 to License NPF-43,adding Special Test Exception to Allow Rc Temperatures Up to 212 Degrees F During Hypostatic or Inservice Leak Testing While in Operational Condition 4 W/O Operational Condition 3 ML20211J1971997-09-29029 September 1997 Application for Amend to License NPF-43,relocating Selected Requirements & Associated Bases from TS to Ufsar.Rev of TS Index & List of Tables to Reflect Relocation Requested 1999-09-24
[Table view] |
Text
G.
Fermi 2 6400 North Dixie llwy., Newport, MI 48166 Detroit Edison 1
10CFR50.92 September 10,1999 NRC-99-0072 U. S. Nuclear Regulatory Commission Attention: Document Control Desk Washington D C 20555-0001
References:
- 1) Fermi 2 NRC Docket No. 50-341 NRC License No. NPF-43
- 2) NRC Letter to Detroit Edison, " Fermi 2 -Issuance of Amendment i
Re: Replacement of the Division II 130/260-Volt DC Battery",
I dated July 9,1999
- 3) Detroit Edison Letter to NRC, NRC-99-0002, " Transmittal of Revision 2 to Fermi 2 Improved Technical Specification Submittal", dated January 26,1999
- 4) Detroit Edison Letter to NRC, NRC-99-0050, " Transmittal of Revision 7 to Fermi 2 Improved Technical Specification Submittal (TAC No. MA1465)", dated June 24,1999
- 5) ANSI /IEEE Standard 450-1972," Recommended Practice for Maintenance, Testing and Replacement of Large Stationary Type Power Plant and Substation Lead Storage Batteries."
- 6) ANSI /IEEE Standard 485-1983," Recommended Practice for Sizing Large Lead Storage Batteries for Generating Stations and Substations."
Subject:
Proposed Technical Specification Change (License Amendment) for the Division I 130/260 VDC Battery Replacement Pursuant to 10CFR50.90, Detroit Edison hereby proposes to amend Operating License NPF-43 for the Fermi 2 plant by incorporating the enclosed changes into the 9909150006 990910 fm
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NRC-99-0072 Page 2 Plant Technical Specifications (TS) Surveillance Requirements (SR) 3.8.4.1,3.8.4.6, 3.8.6.2 and Surveillance Requirement Bases Section 3.8.6.2. The proposed TS
- amendment revises surveillance requirements and the Bases for the Division I Battery System to agree with the design of the new battery replacement. Detroit Edison plans to install the new battery during the Seventh Refueling Outage (RF07),
which is presently scheduled to begin in the spring of the year 2000. Approval of this proposed license amendment is requested by March 2000, with implementation prior to startup from RF07. provides a description and evaluation of the TS proposed changes. provides an analysis of the significant hazards consideration assessment using the standards in 10CFR50.92. provides marked up pages of the TSs to show the proposed changes.
Because Fermi 2 is in the process of converting to the Improved Technical Specifications (ITS) and is expected to have converted to the ITS prior to startup from RFO7, the proposed changes are provided in ITS format, based on the most recent ITS conversion package submitted to the NRC. A typed version of the affected TS pages with the proposed changes incorporated has not been provided at this time as is normally done. This is due to the significant ITS conversion activity that will have taken place concurrent with the preparation of this submittal.
The NRC issued Amendment No.121 to the Fermi 2 Facility Operating License on July 9,1998 (Reference 2). Amendment 121 revised TS Surveillance Requirements for the Division II 130/260 VDC battery system to agree with the design of the new battery replacement that occurred in the Sixth Refueling Outage (RFO6). The new battery for the Division I 130/260 VDC battery system is equivalent in battery type, manufacturer, specific gravity, and number of cells as the Division 11130/260 VDC battery.
Detroit Edison has evaluated the proposed TS changes against the criteria of 10CFR50.92 and determined that no significant hazards consideration is involved.
The Fermi 2 Onsite Review Organization (OSRO) has reviewed and recommended approval of the proposed changes. The Nuclear Safety Review Group (NSRG) has also reviewed the proposed TS changes and concurs with the enclosed determinations. In accordance with 10CFR50.91, Detroit Edison is providing a copy of this letter to the State of Michigan.
1 I
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e USNRC NRC-99-0072 Page 3 j
Should you have any questions or require additional information, please contact Mr. Norman K. Peterson of my staff at (734) 586-4258.
Sincerely, (MLQGT~
0 Enclosures i
1 cc:
A. J. Kugler A. Vegel NRC Resident Office Regional Administrator, Regien III Supervisor, Electric Operators, Michigan Public Service Commission
USNRC NRC-99-0072 Page 4 t
4 I, WILLIAM T. O'CONNOR, JR., do hereby affirm that the foregoing statements are based on facts and circumstances which are true and accurate to the best of my knowledge and belief.
{A) h 0b N
WILLIAM T. O'CONNOR, J Assistant Vice President, Nuclear Assessment On this
/
day of de274/1/d241999 before me personally appeared William T. O'Connor, Jr., being'first duly sworn and says that he executed the foregoing as his free act and deed.
l Ut LWu N'otary Public
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ROSALIE A. ARMBTA unggh!$MppgC0g4Ty ei MYc l^
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l ENCLOSUREITO NRC-99-0072 FERMI 2 NRC DOCKET NO 50 341 OPERATING LICENSE NPF-43 REQUEST TO REVISE TECHNICAL SPECIFICATIONS FOR THE DIVISION I 130/260 VDC BATTERY REPLACFMENT DESCRIPTION AND EVALUATION OF THE PROPOSED CHANGES
Enclosure I to -
NRC-99-0072
. Page 2 DESCRIPTION:
The proposed changes involve revising Technical Specification (TS) Surveillance Requirements
-(SR) 3.8.4.1,3.8.4.6,3.8.6.2 and SR Bases Section 3.8.6.2 to agree with the replacement of the Division I 130/260 VDC station batteries. As part of the ongoing Fermi 2 conversion to the Improved Technical Specification (ITS) format, the Electrical Power Systems TS and associated Bases have been submitted to the NRC and are undergoing review (References 3 and 4).
The direct current (de) electrical power system provides de emergency power via the 130/260 VDC (Class 1E and Balance of Plant) systems and the 24/48 VDC system. The function of the Class' IE 130/260 VDC system is to provide de power to Class IE de loads and for the control and switching of Class IE systems. This power is provided through two sets (Divisions I and II) of 130/260 VDC Category 1 station batteries with full capacity battery chargers. The Division 1
' 260 volt battery (2PA) consists of two 130 volt battery banks (2A-1 and 2A-2) connected in series.
The existing Division I batteries have sufficient capacity to support the Fermi Design Basis Accident load profile; however, a trend in decreasing battery capacity has been seen during battery performance discharge testing. Recent battery performance testing indicated increased signs of degradation in battery capacity for both the 130 VDC 2A-1 and 2A-2 batteries. It should be noted that even with this degradation, the existing batteries meet the present design requirements for assuring the batteries are capable of performing their functions and will be maintained above the criteria for battery replacement (as described in Reference 5, Section 6) until they are replaced.
The existing Division 1260 VDC battery was supplied by C&D Power Systems Inc. This battery is a KC-17 type, lead calcium,1.215 specific gravity and contains 120 cells (includes two 130 VDC battery banks containing 60 cells each). The existing Division I battery will be replaced j
with a higher capacity battery furnished by C&D Technologies Inc. The new battery will be a i
LCR-21 type, lead calcium,1.215 specific gravity and contain 116 cells (includes two 130 VDC battery banks containing 58 cells each). The batteries are scheduled to be replaced during the j
.3eventh Refueling Outage (RF07)..
]
The battery replacement will not change the existing battery system configuration. The new Division I 260 VDC battery will remain located in the Auxiliary Building Division I Battery Room and will continue to supply de power through a set of 130 VDC station batteries. The battery replacement will increase the battery capacity and decrease the number of cells per battery
. system.
The replacement of the Division I 130/260 VDC battery provides benefits for the de power system. The benefits include providing more capacity than the present batteries and increasing the battery charger voltage margin during equalize charge.
l I
p Enclosure I to NRC-99-0072 Page 3 EVALUATION:
J
' DeAroit Edison plans ' o replace the Division I 130/260 VDC station batteries. As stated above, t
the primary differences between the old and new batteries are the battery capacity and number of cells per battery system. The existing Division I battery system (120 cells) is being replaced with a physically larger and higher capacity battery consisting of 116 cells.
The 116 cell battery replacement meets all the requirements of the existing 120 cell battery since
' the end of system discharge voltage of the new battery is the same as the original design for maintaining a minimum allowable battery system voltage of 210 VDC (includes two 130 VDC batteries each maintaining a minimum battery system voltage of 105 VDC). The 116 cell battery is physically larger as it requires larger size capacity cells to maintain the same minimum allowable battery system voltage.
The new battery meets the 210 VDC minimum battery system voltage because the new battery end of discharge volts per cell (V/ cell) is greater than the present system. The present 120 cell battery is designed for an end of discharge battery voltage (minimum cell voltage) of 1.75 V/ cell.
1.75 V/ cell x 120 cell = 210 VDC (i.e.,105 VDC + 105 VDC)
Since the new 116 cell battery contains fewer cells, the minimum cell voltage rnust be held at a higher value to maintain the same minimum allowable battery system voltage of 210 VDC. The new 116 cell battery is designed for a minimum cell voltage of 1.81 V/ cell.
1.81 V/ cell x 116 cell = 210 VDC (i.e.,105 VDC + 105 VDC)
The new battery cell rating will have an increased capacity of over two times the existing battery cell rating. Battery capacity is rated in ampere-hours, which determines how long it will operate at a given discharge rate. The existing battery is designed to supply de power to all required loads for 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> (with a loss of ac power), without the minimum cell voltage dropping below 1.75 volts. The 4 hour4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> rated capacity of the existing battery to 1.75 V/ cell is 560 ampere-hours.
The new battery is designed to supply de power under the same conditions as described, but without the minimum cell voltage dropping below 1.81 volts. The 4 hour4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> rated capacity of the new battery to 1.81 V/ cell is 1200 ampere-hours.
Since the end of system discharge voltage is the same, the new batteries will continue to have sufficient capacity to provide power to essential loads, in the event power to the chargers should be lost. The charge on the new batteries will be maintained by the existing battery chargers. The only change to the chargers will be a change to the setpoints to account for the difference in the number of cells per battery system. The setpoint changes are consistent with manufacturer's recommendations. ' Additionally, changing the battery system from 120 to 116 cells reduces the concem of the Division I battery chargers tripping on high voltage during equalize charging.
. Using fewer battery cells allows the setpoint band between the high voltage shutdown and
Enclosure I to NRC-99-0072 Page 4 equalizing voltage to be widened from approximately one volt to approximately three volts as shown in the table below:
Division I Battery Charcer Setnoint Chances i
~^
Description Existing Setpoint New Setpoint j
i High Voltage Shutdown 138.5 VDC (2.31 V/ cell) 138.5 VDC (2.39 V/ cell)
Equalize Voltage 137.5 VDC (2.29 V/ cell) 135.5 VDC (2.34 V/ cell)
High Voltage Alarm 136.0 VDC (2.27 V/ cell) 134.0 VDC (2.31 V/ cell)
Float Voltage 133.0 VDC (2.22 V/ cell) 129.0 VDC (2.22 V/ cell) 1 Low Voltage Alarm 128.5 VDC (2.14 V/ cell) 124.2 VDC (2.14 V/ cell)
' Discharged Battery is 105 VDC (1.81 V/ cell for Divisions I and Division II)
The existing and the new Division I battery system was sized in accordance with Reference 6.
i Reference 6 recommends a design margin of 10 - 15 percent and an aging factor of 1.25 (20 years) to be used in the design of a de system. A design margin of 10 percent and an aging factor of 1.25 (20 years) were used to determine the size of the new battery system.
This TS amendment is proposing to change: the 7 day and 18 month surveillance requirements
-(TS Sections SR 3.8.4.1 and SR 3.8.4.6) for the battery system terminal voltage on float charge I
and the minimum battery charger voltage; and the 92 day surveillance requirement and Bases (TS Section SR 3.8.6.'2 and Bases SR Section 3.8.6.2) for overcharge battery voltage to correspond to the requirements of the replacement batteries. Each requested TS change is defined and described below, corresponding to the changes provided in markup format in Enclosure 3.
1.
Channe to Surveillance Requirement 3.8.4.1:
TS Surveillance Requirement 3.8.4.1 states that once per 7 days," Verify battery terminal voltage is 2130 V for Division I and 2125.7 V for Division II on float charge." This surveillance requirement will be changed to state, " Verify battery terminal voltage is 2125.7 V on float charge." Under normal operating conditions, the battery chargers produce a de output, which
" float" derges the batteries. This new terminal (charging) voltage is acceptable because it is based on the same individual cell voltage as the existing 130 volt,1.215 specific gravity, lead calcium,60 cell system covered in the present T.S.
Existing:
(130 volts) / (60 cells) = 2.167 volts / cell
'New; (2.167 volts / cell) x (58 cell) = 125.7 volts The basis for the battery terminal float voltage ensures the effectiveness of the charging system and the ability of the batteries to perform their intended function. Float charge is the condition in
~
. to NRC-99-0072 Page 5 which the charger is supplying a continuous charge required to overcome internal losses of a battery (or battery cell) and maintain the battery (or a battery cell) in a fully charged state.
2.
Channe to Surveillance Reauirement 3.8.4.6:
TS Surveillance Requirement 3.8.4.6 states that once per 18 months, " Verify each required battery charger supplies for Division I: 2100 amps at 2129 V for 2 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />; and Division II: 2 100 anies at 2124.7 V for 2 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />." This surveillance requirement will be changed to state,
" Verify each required battery charger supplies 2100 amps at 2124.7 V for 2 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />." This new battery charger terminal voltage for Division I is acceptable because it is based on the same individual cell voltage as the existing 130 volt,1.215 specific gravity, lead calcium,60 cell system covered in the T.S.
Existing:
(129 volts) / (60 cell) = 2.15 volts / cell New:
(2.15 volts / cell) x (58 cell) = 124.7 volts 1
The minimum voltage of 124.7 volts (or 2.15 volts / cell), ensures that the battery can be maintained charged. The minimum voltage of 2.15 volts / cell is greater than the required continuous minimum cell float voltage of 2.13 volts / cell required by T.S. Table 3.8.6-1.
Therefore, the surveillance requirement of the battery charger supplying this minimum voltage of 124.7 volts (or 2.15 volts / cell) at the chargers rated ampacity is acceptable.
3.
Channe to Surveillance Reauirement 3.8.6.2 and Bases:
TS Surveillance Requirement 3.8.6.2 states, " Verify battery cell parameters meet Table 3.8.6-1 Category B limits," once every 92 days "AND once within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> after battery overcharge >
150 V for Division I and > 145 V for Division II." This surveillance requirement of verifying individual cells after an overvoltage condition will be changed to state. "AND once within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> after battery overcharge > 145 V." The Bases SR Section 3.8.6.2 also states,"In addition, within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> of a battery discharge < 105 V or a battery overcharge > 150 V for Division I and
> 145 V for Division II, the batterj must be demonstrated to meet Category B limits." This section of the Bases will be change.' to state, "In addition, within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> of a battery discharge
< 105 V or a battery overcharge > 145 V, the battery must be demonstrated to meet Category B limits." This new battery terminal overvoltage for Division I is acceptable as it is based on the same individual cell voltage as the existing 130 volt,1.215 specific gravity, lead calcium,60 cell system covered in the T.S.
Existing:
(150 volts) / (60 cell) = 2.5 valts/ cell New:
(2.5 volts / cell) x (58 cell) = 145 volts i
' to NRC-99-0072 Page 6 i-4 4
i l
This new overvoltage (or overcharge) value is acceptable as no immediate damage would be seen by the battery at this level. Overvoltage,if extreme and uncorrected for extended periods, will cause corrosion on the batteries' positive plates, increase cell temperatures and increase water consumption. This voltage of 145 volts (or 2.5 volts / cell) is acceptable, as it is slightly greater then the maximum continuous recommended equalize charge voltage for the new and existing battery of 2.38 volts / cell.
SIGNIFICANT H AZARDS CONSIDERATION:
In accordance with 10CFR50.92, Detroit Edison has made a determination that the proposed amendment involves no significant hazards considerations. To make this determination, Detroit Edison must establish that operation in accordance with the proposed amendment would not: (1) involve a significant increase in the probability or consequences of an accident previously j
evaluated; or (2) create the possibility of a new or different kind of accident from any accident i
l previously evaluated; or (3) involve a significant reduction in a margin of safety. The significant hazards consideration assessmeat is presented in Enclosure 2.
ENVIRONMENTAI, IMPACT:
Detroit Edison has reviewed the proposed Technical Specification change against the criteria of 10CFR51.22 for environmental considerations. The proposed changes do not involve a significant hazards consideration, nor significantly change the types or significantly increase the amounts of effluents that may be released offsite, nor significantly increase individual or cumulative occupational radiation exposures. Based on the foregoing, Detroit Edison concludes that the proposed Technical Specifications do meet the criteria given in 10CFR51.22(c)(9) for a categorical exclusion from an environmental review.
CONCI USION:
Based on the evaluation above: 1) There is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner, and 2) such activities will be j
conducted in compliance with the Commission's regulations and proposed amendments will not i
be inimical to the common defense and security or to the health and safety of the public.
l J
ENCLOSURE 2 TO NRC-9S-0072 FERMI 2 NRC DOCKET NO 50 341 OPERATING LICENSE NPF-43 i
REQUEST TO REVISE TECHNICAL SPECIFICATIONS FOR THE DIVISION I 130/260 VDC BATTERY REPLACEMENT 10CFR50.92 EVALUATION
l
. to NRC-99-0072 Page 2 HASIS;FOR SIGNIFICANT IIAZARDS DETERMINATION:
The proposed Technical Specification changes described in Enclosure 1 do not involve a significant hazards consideration for the following reasons:
1.
The changes do not involve a significant increase in the probability or consequences of an accident previously evaluated.
The proposed changes do not involve a change in the manner in which the plant is operated.
TS Sections 3.8.4.1,3.8.4.6,3.8.6.2 and Bases Surveillance Requirement Section 3.8.6.2 are being revised to reflect the new Division I battery cell / system characteristics and associated requirements. The new battery will have an increased capacity over the present battery, while maintaining the existing battery system voltage requirements. This is possible because the present and new battery specific gravity (1.215) and type (lead calcium) are the same. Also, the end of battery system discharge volage remains the same as 210 VDC. The Division I batteries will continue to furnish power to redundant essential i
loads as required and as designed. The new surveillance requirement voltages are based on the same volts / cell criteria used for the existing batteries. Furthermore, failure or malfunction of the station batteries does not initiate any of the analyzed accidents previously evaluated in the UFSAR. The changes described will therefore not involve an i
increase in the probability or consequences of an accident previously evaluated.
2.
The changes do not create the possibility of a new or different kind of accident from any accident previously evaluated.
The new battery is Class IE qualified equipment and is being maintained within the same overall design parameters as tre existing battery. That is, the battery terminal voltage on float voltage conditions (2.16~! volt / cell), overvoltage conditions (2.5 volts / cell) and charger capability (2.15 volts / cell) are the same as the original design. Furthermore, the end of j
system discharge voltage of the battery system is maintained the same; therefore, there is no negative impact to plant loads supplied by the batteries. Failures of the batteries and j
chargers have been considered in both the existing and modified configurations. The proposed changes will not change performance or reliability nor introduce any new or different failure modes or common mode failure and will therefore not create the possibility of a new or different kind of accident from any accident previously evaluated.
3.
The changes do not involve a significant reduction in the margin of safety.
The changes act to increase overall battery capacity from 560 ampere-hours to 1200 ampere-hours with the minimum battery discharge voltage remaining at 210 VDC (or 105 VDC per battery). The battery terminal voltage on float voltage conditions (2.167 volt / cell), overvoltage conditions (2.5 volts / cell) and charger capability (2.15 volts / cell) are the same as the original design. The new surveillance requirement voltages are based on
' to NRC-99-0072 Page 3 the same volts / cell criteria used for the existing batteries. The batteries' ability to satisfy the design requirements (battery duty cycle) of the de system will not be reduced from original plant design and will therefore not have any negative impact to plant loads the battery supplies. The proposed changes therefore do not involve a teduction in the margin of safety.