Similar Documents at Fermi |
---|
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-98-0062, 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-98-0057, 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-98-0033, 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-98-0003, 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-98-0027, 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-98-0002, 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-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 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 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 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 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-98-0062, 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-98-0057, 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-98-0033, 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-98-0003, 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-98-0027, 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-98-0002, 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-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 ML20133L6171997-01-0202 January 1997 Amend 11 to License DPR-9,allowing Certain Equipment & Instruments to Be Removed from Svc for Short Periods of Time Allowing for Maint,Testing,Insp & Account for Equipment Failures 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 1999-09-24
[Table view] |
Text
_ _ _ _ _ _ _ . _ _
3' . p B. Rdph Sylvb 9'
- Seneor %ce Preudent Detroit .,,,,,o,,,,_,,
EdlSO Newport. Midugan 48166 (313) 56fr 4150 May 31, 1989 NIC-89-Oll5 U. S. !bclear Regulatory Commission Attn: Document Control Desk Washington, D. C. 20555
References:
- 1) Fermi 2 NIC Docket No. 50-341 NFC License No. NPF-43
- 2) Detroit Edison Letter to NIC, NIC-89-0052,
" Proposed Operating License / Technical Specifications Change (License Amendment) -
Cycle 2 Reload Submittal", dated April 3, 1989
Subject:
Proposed Technical Specification Changes to Allow Operation with an Extended Operatino Domain Pursuant with 10CFR50.91 and 50.92, Detroit Edison hereby proposes to amerd Operating License NPF-43 for the Fermi 2 plant by incorporating the enclosed changes into the Plant Technical Specifications. The proposed changes modify the Average Power Range Monitor flow biased rod block and scram limits to allow up to 100% power operation of Fegmi 2 with core flow reduced to as low as 87% of rated with up to a 50'F reduction of rated final feedwater temperature. Appropriate changes to the Bases are also proposed.
Operation in the extended operating domain with either normal or reduced feedwater heating is supported by evaluations and analysis performed for Detroit Edison by GE Nuclear Energy. These analyses have been performed for Fermi 2's current operating cycle (Cycle 1) and for the upcoming Cycle 2. The analysis submitted for Cycle 2 in Reference 2 included operation in the expanded domain. However, the Technical Specification changes in Reference 2 did not include provisions for operating in the expanded domain. This submittal provides the needed Technical Specification provisions.
Attachment 1 provides the Summary, Description of Changes, Significant Hazards and Environmental Impact Considerations for Cycle 1 and Reference 2 extends this for operation in the upcoming Cycle 2 l operation. Attachment 2 provides a summary listing of the proposed l Technical Specification and Bases changes for operation in the I extended domain for both Cycle 1 aid Cycle 2, Reload 1 Atterhment 3 1 ~g90613OO96 890531 , 4, PDR ADOCK 05000341 p PDC )[
_- - - - - - _ _ - - - - _ - _ _ - - -____ D
r .
[ , 'l* ' ggge j May 31, 1989
- IGC-89-Oll5 Page 2 is a copy of the marked up Technical Specification ani Bases pages for both Cycle 1 and Cycle 2, Reload 1. Enclosures 1 through 3 contain the GE lbclear Energy analysis and supporting work.
Approval of these changes will provide Fermi 2 with greater operating flexibility and a greater capacity factor. Prompt review and approval of this proposal is requested for both Cycle 1 and Cycle 2, Reloa31.
Detroit Edison has evaluated the proposed Technical Specifications against the criteria of 10CFR50.92 and has determined that no significant hazards consideration is involved. The Fermi 2 Chsite Review Organization has approved and the Nuclear Safety Review Group has reviewed the proposed Technical Specifications and concurs with the enclosed determinations. In accordance with 10CFR50.91, Detroit B31 son has provided a copy of this letter to the State of Michigan.
If you have any questions in this matter, please conta:t Mr. Glen Ohlemacher at (313) 586-4275.
Sincerely, Enclosure cc: A. B. Davis R. C. Knop W. G. Rogers J. F. Stang Supervisor, Advanced Planning and Review Section, Michigan Public Service Commission
-- ----- - . - - - - - - - - - . - - - - - - - - = - - - - - - - -. . .
f x
c , .
USNRC-' -
May 31, 1989-
- 3-
~
NRC-89-Oll5 1 Page.3 l
I, B. RALPH SYLVIA, do hereby affirm that the foregoing statements are based best of on myfacts knowledgeand circumstances and belief. which are true:and accurate to the l-f..
B.RALPdSYLVM !
Senior Vice President l l
l I L <
[ On this - 8 g/ day of. Oh !
, 1989, before me personally appeared B. Ralph Sylvia, l#ing first duly sworn and says '
that he executed the foregoing as his Tree act and deed. i l
.. I h Notary Public !
DOSADE A ARMET14 ,
Notary Public. Mon oa County. Mi l MyCommission ExpuesJan.11,1992 1
- . , n . .
g,,
-p .
I ag 3 ATTACHMENT 1-
SUMMARY
,' DESCRIPTION.OF-CHANGES, SIGNIFICANT HAZARDS' l- 'AND ENVIRONMENTAL IMPACT CONSIDERATIONS.
l' c
I' 1
- 3 Page 1 of 12 Attachment 1 NRC-89-0115 JNTRO9UCTION Chapters 4 and 15 of the Fermi 2 Updated Final Safety Analysis Report (UFSAR) describe the-power / flow allowed operating domain.
Because Boiling Water Reactor (BWR) operating experiences have long-indicated that an expanded power / flow operating map can be very b:.neficial to the operation of a plant, Detroit Edison has determined the feasibility of such an expansion at Fermi 2. This larger operating domain will provide increased operational flexibility and improved capacity . factor at Fermi 2. Specific
'oenefits include:
- 1) Faster power ascension to rated power because it facilitates higher rod line patterns set during low xenon startups and flow compensation for xenon buildup.
- 2) Rated power can be maintained longer without adjustment of control rods by using the additional flow range to compensate for reactivity reduction from fuel burnup This will improve the capacity factor since control rvd adjustments must be performed at reduced power levels due to fuel limitations.
- 3) Improved fuel utilization and consequently enhanced fuel cycle economics by use of the flow control spectral shift operating strategies.
Normal power range operation in along or below the 102% flow control line and the 100% core thermal power line (see Figure 1, attached). The current power / flow map is described in UFSAR Section 4.4.3.3 (UFSAR Figure 4.4-4) and UFSAR Section 15.0.3.3.3 (UFSAR Figure 15.0-3) of the Fermi 2 UFSAR. The proposed expanded region is referred to herein as the Extended Load Line Limit Region (ELLLR) and is bounded at the top by a new APRM (Average Power Range Monitor) Rod Block line (0.58W + 50%) up to 100% power /87%
flow, the 100% thermal power line, and the 100% flow line. W is the per cent recirculation drive flow. The left and right side of the power / flow map remain unchanged. The proposal requires that two present operating constraints remain: 1) feedwater temperature reduction up to 50 F of rated feedwater temperature and 2) core inlet subcooling must be less than 45 Btu /lbm. These restrictions l
are presently assured by plant procedures. The core inlet i
subcooling requirement was made in response to a concern uncovered in the Enclosure 1 analysis.
This proposal changes the slope and intercept of the flow biased APRM rod block and scram lines (Table 2.2.1-1, Specification 3/4.2.2, and Table 3,3.6-2) to allow operation in the Extended Load Tine Limit Region (ELLLR). An addition in the MCPR Bases (B t
b- -
3 Page 2 of 12 Attachment 1 NRC-89-0115 3/4.2.3) section states that the K, curves are still valid for the extended domain even though they were derived using the 100% flow control line.
EVALUATION Detroit Edison's evaluation of this proposal is based on the results of a General Electric Nuclear Energy (GE) Fermi 2 specific analysis which fully bounds the ELLLR. This analysis (Enclosures 1 through 3) evaluates the extension of the operating domain to include the entire Maximum Extended Load Line Limit Region (MELLLR) with continued operation for either normal or reduced feedwater heating (up to a 150'F reduction) for Cycle 1. Thn proposal requires that two present operating constraints remain: 1) feedwater temperature reduction up to 50 F of rated feedwater temperature and 2) core inlet subcooling must be less than 45 Btu /lbm. These restrictions are presently assured by plant procedures. The core inlet subcooling requirement was made in response to a concern uncovered in the Enclosure 1 analysis.
The MELLLR is bounded by the 100% power line for the flow range of 75% to 100% of rated, its corresponding power / flow constant line, and the 100% rod line. Detroit Edison is presently pursuing neither the expansion of the allowable feedwater heatiTig range beyond the 50 F reduction of rated feedwater temperature currently allowed by the Cycle 1 analysis in the normal operating domain nor the full MELLLR domain as evaluated by GE; however, the analysis results and impact evaluation for the full MELLLR domain with reduced feedwater heating are conservatively applicable to operation in the proposed ELLLR domain. The evaluation for
! application to Cycle 2, Reload 1 is included in Reference 2. The evaluations for the ELLLR extended operating domain include:
- 1. Transient Performance
- 2. Overpressure Protection
- 3. Loss of Coolant Accident Peak Cladding Temperature l
1
- 4. Containment Pressure Temperature and Hydrodynamic Loads
- 5. Thermal 3ydraulic Stability Transient Performance ,
1 All anticipated and abnormal operational transients described in Chapter 15 of Fermi 2 UFSAR were examined in the ELLLR.
)
Y a
y ,;..
Page 3 of 12 Attachment 1 NRC-89-0115 Three limiting events were analyzed in detail. They were:
- 1. Turbine / Generator Trip with Bypass Failure (T/GTNBP)
- 2. Feedwater Flow Controller Failure (FWCF)
- 3. 100*F Loss of Feedwater Heating (LFWH)
The evaluation has been performed at bounding power / flow operating points outside the ELLLR with normal and reduced feedwater heating. The evaluation showed that the transient performance in the ELLLR with up to 50 F reduction of rated final feedwater temperature is bounded by the transient performance in the normal operating power / flow map. It is concluded that the results of the current UFSAR Chapter 15 transient analysis adequately bound the transient performance for ELLLt1.
The Rod Withdrawal Error (RWE) transient is mitigated by the Rod Block Monitor System (RBM) setpoint. The transient severity of a RWE in the ELLLR is bounded by the current UFSAR analyses with the existing RBM setpoints. For operation in the ELLLR extended operating domain, the rod block will occur sooner; therefore, resulting in a less severe transient.
Overpressure Protection The slightly lower initial steam flow and operating pressure when operating in the ELLLR with either normal or reduced feedwater heating provide better overpressure protection for the analyzed most limiting Main Steam Line Isolation Valve (MSIV) closure flux scram ever.t. Therefore, the UFSAR Chapter 6 overpressure protection analysis adequately bound operation in the ELLLR.
Loss of Coolant Accident Peak Claddina Temperature Operation in ths ELLLR results in operation on a higher rod line which will permit a higher power (higher initial stored !
energy in the fuel) at a given flow. This increases the <
probability of losing nucleate boiling at the highest power axial node prior to the time of jet pump uncovery. This phenomenon is called early boiling transition (BT) and could affect the calculated Peak Cladding Temperature (PCT).
There are two parameters which play a major role in determining the calculated PCT that are affected by the higher core power at lower core flow: (1) the time of boiling transition at the high power axial node of the limiting fuel l
)
F 4 Page 4 of 12 Attachment 1 NRC-89-0115
- assembly and (2) the calculated core uncovery duration. Early boiling transition results in a less efficient removal of the initial stored energy from the fuel, which tends to increase the calculated PCT. Lower initial core flow tends to decrease the calculated PCT. This occurs because increased subcooling in the downcomer and lower plenum at lower core flows increases the initial system inventory. The increased system inventory leads to a shorter core uncovery duration and lower calculated PCT.
The variation of the bundle inlet flow during a LOCA event is determined by a number of parameters, including the break size, the water inventory in the reactor at the start of the event, cnd the steady-state core power and flow conditions.
The first of these is accounted for in the current UFSAR LOCA analysis. The effect of variations in the remaining two was accounted for by performing an analysis at the limiting power flow point along the ELLLR boundary. The initial MCPR is also an important parameter in determining whether or not early boiling transition will occur at the high power axial node.
Credit was taken for the Technical Specification requirement on MCPR versus core flow (K,) with an additional 2%
conservatism added to satisfy 10CFR50 Appendix K, A LOCA analysis was performed for Fermi-2 at the 102% power and 75% flow condition outside the ELLLR to bound the ELLLR.
This condition was selected because it is the lowest core flow at which Fermi-2 can operate with a unadjusted MCPR operating limit. The results of this calculation show that early BT does not occur. Thus, the calculated PCT is less than that of the UFSAR case. Therefore, it is concluded that the current UFSAR Chapter 6.3 calculated PCT adequately bound the ELLLR results.
A 50 F reduction of final feedwater temperature results in increased system mass in the vessel due to increased subcooling and decreased break flow rate at most times during a LOCA (ne to lower initial vessel pressure and steam production. The increased system mass and the decreased break flow act together to result in a delay in the time of dryout, an increase in the time between dryout and lower plenum flashing, and a delay in the time to core uncovery. As a l result, the peak cladding temperature for operation with reduced feedwater temperature is lower than when operating at rated feedwater temperatm o. This conclusion applies for operation in both the no. ;I and ELLLR operating domain.
Y _ __-__-_-
g . .
- Page 5 of 12 Attachment 1 NRC-89-0115 Containment Responses and Loads Operation in the ELLLR extended operating region leads to a higher core inlet subcooling and consequently to a higher LOCA blowdown flow rates, compared with those presented in the containment analysis section of the UFSAR, for certain time periods following the double-ended guillotine break of a recirculation suction line. However, an analysis has been performed to show the peak drywell pressure, temperature and peak suppression pool pressure are all within the design values reported in Chapter 6.2 of UFSAR.
An evaluation was also performed to determine the impact of operation in the ELLLR with reduced feedwater heating on LOCA containment hydrodynamic loads. The containment hydrodynamic loads including pool swell, condensation oscillation, chugging and vent system thrust loads are all within their corresponding design values provided inlet subcooling is less than 45 BTU /lbm. At the present time Detroit Edison is administratively controlling operations so as to remain under 45 BTU /lbm subcooling at the reactor pressure vessel inlet.
Furthermore, Detroit Edison is not proposing a relaxation of current final feedwater temperature constraints.
Thermal Hydraulic Stability Operation in the ELLLR results in operating on a higher control' rod line which could potentially reduce stability margin. However, the stability compliance of all licensed GE fuel designs have been demonstrated on a generic basis for operation in the normal as well as the ELLLR operating domain with or without reduced feedwater heating. In NRC evaluation reports, the Staff concluded that GE fuel designs meet the stability criterion set forth in 10CFR50, General Design Criteria 10 and 12, provided that the BWR utility has in place operating procedures and Technical Specifications which are l
consistent with the recommendations of GE SIL-380 to assure detection and suppression of global and local instabilities.
Since Fermi 2 Technical Specifications and procedures are consistent with SIL-380 recommendations, operation in the ELLLR will meet all stability criteria.
Both the GE SIL-380 recommendations and the more conservative GE interim corrective actions, which have resulted from recent thermal-hydraulic instabilities, have been included in the Fermi 2 operating procedures. Regions of restricted operation defined in Attachment 1 to NRC Bulletin No. 88-07 Supplement 1, are applicable to Fermi 2 Cycle 1 and Reload 1, Cycle 2.
Page 6 of 12 f Attachment 1 NRC-89-0115 SIGNIFICANT HAZARDS EVALUATION In accordance with 10CFR50.92, Detroit Edison has reviewed the attached proposed Technical Specification and has concluded that it does not involve a significant hazards consideration. The basis for this conclusion is that the criteria of 10CFR50.92(c) are not compromised. All anticipated and abnormal transients described in the Fermi 2 UFSAR Chapter 15 were examined for operation in both the MELLLR (Maximum Extended Load Line Limit Region) and the normal operating power / flow map. Evaluations were performed at two power / flow operating points (102% power /75% flow and 102%
power /100% flow) with rated feedwater temperature reduction of 15 0'F .
The proposed amendment allows operation in a smaller ELLLR operating domain. This ELLLR operating domain is bounded at the top by the proposed new APRM (Average Power Range Monitor) Rod Block line (0.58W + 50%) up to 100% power /87% flow, the 100%
thermal power line, and the 100% flow line. W is the per cent recirculation drive flow. The proposal requires that two present constraints remain: 1) feedwater temperature reduction operating up to 50 *F of rated feedwater temperature and 2) core inlet subcooling must be less than 45 Btu /lbm. These restrictions are presently assured by plant procedures.
- 1. The amendment does not involve a significant increase in the probability or consequences of an accident previously evaluated.
Operation in the ELLLR (Extended Load Line Limit Region) with the specified feedwater temperature reduction and core inlet subcooling operational constraints has . no effect on the probability of occurrence of any transient because plant equipment and systems still operate within their design limits.
The following transients were potentially limiting under the proposal but were determined to be bounded by the UFSAR analysis (refer to Enclosure 1, Chapters 1 and 2). The delta
, CPR (Critical Power Ratio) analysis took credit for the Technical Specification requirement on MCPR (Minimum Critical i
Power Ratio) versus core flow K, factor with an additional 2%
conservatism.
l I
l L - _--
C Page 7 of 12 Attachment NRC-89-0115 Transient Limitina Concern Turbine / Generator Trip with Bypass Failure delta CPR RPV Pressure Feedwater Flow Controller Failure with delta CPR Bypass Failure .RPV Pressure Feedwater. Flow Controller Failure without delta.CPR Bypass Failure RPV Pressure 100*F Loss of Feedwater Heating delta CPR Main Steam Isolation valve Closure RPV Pressure Loss of Coolant Accident delta CPR Peak Clad Temperature Containment'(Enclosure 1/ Chanter 5. Enclosure 2 and 3)
For Peak: Drywell Pressure, operation in the MELLLR with reduced feedwater temperature of 150*F leads to higher LOCA bPawdown flow rates following a double-ended guillotine break c s recirculation suction line. The limiting condition for-p . drywell pressure is the power / flow condition with highest core inlet subcooling in the MELLLR with reduced feedwater temperature. With a maximum feedwater temperature reduction of 50 F and under the limiting condition, peak drywell
- pressure will not exceed the UFSAR reported value of 56.5 psig (Enclosure 3). The maximum allowable pressure is 62 psig.
For the torus loads it was determined that during a LOCA, vent system thrust loads will likely be larger when initial operating conditions are in the ELLLR. An additional study (Enclosure 2) uncovered that stresses could exceed the maximum
. vent header capability when the core inlet subcooling exceeds 45 Btu /lbm. At the present time Detroit Edison is administratively controlling operations so as to remain under 45 BTU /lbm subcooling in the reactor pressure vessel.
The proposal requires that two present operating constraints remain: 1) feedwater temperature reduction up to 50'F of rated feedwater temperature and 2) core inlet subcooling must be less than 45 Btu /lbm. These restrictions are presently assured by plant procedures. Furthermore, Detroit Edison is not proposing a relaxation of current final feedwater temperature constraints.
- g. . .
Page 8 of 12 Attachment 1 NRC-89-0115 4 All other containment parameters are fully bounded by the UFSAR analysis.
Vessel Internals (Enclosure 1/ Chanter 7)
The major concern is acoustic loads for the vessel internals.
These are lateral loads on the vessel internals that result from propagation of the decompression wave created by a sudden recirculation suction line break. Due to increased downcomer subcooling, these loads will increase relative to the UFSAR values, but there is enough design margin to handle the increased loading during operation in the ELLLR.
Detroit Edison concludes that the results of the current UFSAR transient analysis adequately bound the transient performance in the ELLLR with up to 50 F reduction of rated final feedwater temperature. Therefore, the amendment does not involve a significant increase in the consequences of an accident previously evaluated.
- 2. The amendment does not create the possibility of a new or different kind of accident from any previously evaluated.
Operation in the ELLLR has been evaluated with the initial condition of the extended region. There is no change to the plant design required to accommodate the extended region. All plant equipment and systems still operate within their design limits. The proposed APRM simulated thermal power scram and rod block configuration provide the same protection margin to the operating map as the current configuration. No new or different accident are therefore created by the extended domain.
Since operation at the higher rod lines does create the possibility of a slow recirculation flow runout event taking power above the rated core thermal power, the slow recirculation flow runout event was evaluated. The Recirculation Flow Control Failure with the Increased Flow transient is evaluated in the UFSAR Chapter 15.4.5. The slow flow increase case was reviewed with the initial conditions i of the worst case conditions in the MELLLR (which bounds the ELLLR) and it was determined that the existing K, factors remain bounding. The K, factor is designed to maintain core thermal margins in the event of a recirculation flow runout event. That is, K defines a set of MCPR limits as a function of core flow such ,that a flow runout event initiated from any given power / flow point will result in a minimum CPR no less than the safety limit MCPR. Therefore, the slow recirculation
\
- 3 ..
Page 9 of 12 Attachment 1 NRC-89-0115 flow runout event does not create the possibility of a new or different kind of accident from any previously evaluated.
- 3. The proposal does not involve a significant reduction in a margin of safety.
The proposed expansion of the power / flow map has been evaluated to show that all safety criteria are met. .The changes in APRM Rod Block and Trip Setpoint are only to accommodate the operating region. The new setpoints maintain ,
the same maximum values (113.5% maximum for the STPM 1 (Simulated Thermal Power Monitor) scram and 108% for the rod block) at ' rated power / flow conditions and the same margin (6%)
between the STPM scram and rod block setpoints as the current Technical Specification. Furthermore, the transient performance in the ELLLR is bounded by the normal operating domain and all parameters remain within their design limits.
For Peak Drywell Pressure, operation in the MELLLR with reduced feedwater temperature of 150 F leads to higher LOCA blowdown flow rates following a double-ended guillotine break of a recirculation suction line. The limiting condition for peak drywell pressure is the pover/ flow condition with highest core inlet subcooling in the MELLLR With reduced feedwater temperature. With a. maximum feedwater temperature reduction of 50 F and under the limiting condition, peak drywell pressure will not exceed the UFSAR reported value of 56.5 psig (Enclosure 3). The maximum allowable pressure is 62 psig.
For the torus loads it was determined that during a LOCA, vent system thrust loads will likely be larger when initial operating conditions are in the ELLLR. An additional study (Enclosure 2) uncovered that stresses could exceed the maximum .
vent header capability when the core inlet subcoo).5g exceede !
45 Btu /lbm. At the present time Detroit Edison is i administratively controlling operations so as to remain under i 45 BTU /lbm subcooling in the reactor pressure vessel.
For the vessel internals the major concern is the acoustic !
i loading. These are lateral loads on the vessel internals that result from propagation of the decompression wave created by a sudden recirculation suction line break. Due to increased 3 downcomer subcooling, these loads will increase relative to 1 the UFSAR values, but there is enough design margin to handle l the increased loading during operation in the ELLLR. ;
Operation in the ELLLR results in operating on a higher control rod line which could potentially increase the probability of encountering thermal-hydraulic instability.
LT -
Page 10 of 12 Attachment 1 NRC-89-0115
'The NRC has concluded that GE' fuel designs meet the stability--
criterion set forth in 10CFR50 Appendix A, General Design Criteria 10 ' and 12, provided that the BWR has in place operating procedures and Technical Specifications which are consistent with the recommendations of GE SIL-380 to assure detection and suppression of global and local instabilities.
This NRC evaluation includes operation in the ELLLR. Since ,
Fermi 2 Technical Specifications and procedures are consistent '
with SIL-380 recommendations, operation in the ELLLR will meet all stability criteria.
Both the GE SIL-380 recommendations and the more conservative GE interim corrective actions, which have resulted from recent thermal-hydraulic instabilities, have been included in the Fermi 2 operating procedures.. Regiors of restricted operation ,
defined in-Attachment 1 to NRC Bulletin No. 88-07 Supplement !
1, are applicable to Fermi 2 Cycle 1 and Reload 1, Cycle 2 and l have been implemented at Fermi 2. f Therefore, the proposal does not involve a significant l reduction in a margin.of safety.
For the ' proposed changes, it has been demonstrated that the criteria of 10CFR50.92 are satisfied, and so it is judged that no significant hazards considerations exist.
ENVIRONMENTAL IMPACT Detroit Edison Company has reviewed the propose'd Technical Specification changes against the criteria of 10CFR51.22 for environmental considerations. The proposed changes do not' involve a significant hazards consideration, nor increase the types and amounts of effluent 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 Specification changes meet the criteria given in 10CFR51. 22 (c) (9) for a categorical exclusion from the requirement for an Environmental Impact Statement.
CONCLUSION 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 conducted in compliance with the commission's regulations and the i proposed amendments will not be inimical to the common defense and security or to the health and safety of the public.
i - - - - - - - - - - _ _ _ - . _ _ _ _ _ _ _
i:..
)
Page 11 of 12 Attachment 1-NRC-89-0115 I,
These Technical Specification changes reflect the results of transient and accident analyses for both Cycle 1 nnd Reload 1, Cycle 2. The extended operating domain ~ analysis was performed by l GE Nuclear Energy'with the NRC approved methodology. described.in GESTAR. The proposed Technical Specification changes ensure the
. plant conditions remain within the bounds of the' initial conditions of the analyses.
Detroit Edison therefore believes that this proposal is acceptable and requests prompt consideration and approval.
l L
L _- _ _ _ _ _ _ _ _ _ _
.i
- s. , .
- Jage 12 of 12 Attachment 1 NRC-89-0115 Figure 1 EXTENDED POWER-FLOW MAP (ELLLR)
= ,
i j A estulhasesmabattes maTee Maur S. M M 9temsamerpop W = & bMITSP EAMon ,
- s. asan6vstemessen unster meMon O seen pusoeenvasi.
is - #
e,#
- l. . .
_ .i pQ.A
/
f t ,s s.
- p. - - - -
. =
to - Mnem TWuwlg pasmsPsette ,
'- ) I iit I t t SM Weg MSur l