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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-98-0062, 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
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o I/"**vI.e7.m.m OR r -i n Edson !Er?i3* ::m. 4 August 17, 1990 NIC-90-0079 U. S. Ibclear Regulatory Ccanission Attn: Docunent Control Desk Washington, D. C. 20555 Deference: 1) Fermi 2 NIC Docket No. 50-341 NIC License No. IPF-43
- 2) Safety Evaluation PLport, imXi-0798 For Enrico Fermi Unit 2, From Office of lbclear 11eactor P49ulation - July 1981.
- 3) Detteh Illison Ictter to NIC, NIC-89-0100,. [
" Proposed Technical Specification Change ,
(License Anendnent) - Wrbine Overspeed '
Protection System (3/4.3.6)" dated July 24, 1989
- 4) Detroit Itlison I4tter to NIC, EP2-53,907, "Innervice Inspection Program",
dated June 30, 1981 .
i
Subject:
Proposed Technical Specification Change (License Anendnent) - Turbine Overspeed Protection Svctem (3/4.LB) - Regoval Pursuant to 10CFR50.90, Detroit Fxlison Conpany hereby prcposes to !
anend Operating License IFF-43 for the Fermi 2 plant by incorporating j the enclosed change into the Plant Technical Specifications. This ,
. proposal requests renoval of Technical Specification 3/4.3.8 " Turbine Overspeed Protection System" bccause the administrative controls inposcd by this Technical Specification are unnecessary and require the plant to perform periodic powr rMuctions for turbine valve testing. The basis for the subject Standard Tcchnical Specification (TS) involves naintaining the turbine overspeed protection systens to rMuce the hazards of turbine missiles. However, based on the orientation and location of Fermi 2 turbine and the structural design of the plant, Dettoit Edison has concluded that any potentiali;,
generated turbine missile will not prevent the reactor from act61eving and naintaining a safe shutdown coMition. The supporting ana'yses for this conclusion have Men previously reviewed and accepted by the ,
N!C as indicatal in Reference 2, Section 3.5.2.
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USNIC J August 17, 1990 10C-90-0079 Page 2 It was recognized that a potential turbine missile hazard was not the basis for Fermi 2 Overspeed Protection TS at the tine of Termi 2 licensing. Accordingly, the subject TS Bases discusses the reliability benefits of maintaining the turbine overspecd protection system and not the need to maintain the system to reduce the hazards of turbine missiles. Detroit Mison fully recognizes the benefit of performing turbine overspea:1 protection tests and inspections to ensure reliable operation of this station, however, we do not believe thet rigid %chnical Specification requirenents are needed on this system. We are therefore requesting renoval of the Turbine Overspeed Prottetion System TS.
Reference 4 connitted to perform turbine valve inspections and cycling tests. Reference 2, Section 10.2.1, indicates that these inspections and tests are acceptable to the NIC staff and will be includc4 in the Fermi 2 Technical Epocifications. Please note, approval of this proposal will rescind the Referorce 4 commitnents.
Approval of this proposal will nake the Reference 3 prcrosal unnecescary.
Detroit mison has evaluated the proporal Technical Specification against the criteria of 10CFR50.92 and determined that no significant hazards consideration is involved. The Fermi 2 Onsite Review Organization has toproved and the ibclear Safety Review Group has reviewed the proposed Technical Specification and concurs with the enclosed ck. terminations. In accordance with 1(CFR50.91, Detroit Edison is providing a copy of this letter to the State of Michigan.
If you have any questions, please contact Mr. Gordon A. Nader at (313) 586-4513.
Sincerely, nolosure N
cct A. B. Davis R. W. DeFayette W. G. Rogers J. P. Stang Supervisor, 2dectric Operators, Michigan .
Public Service Ccumission - J. R. Pzdgett
US!GC
August 17, 1990 10C-90-0079 Page 3 I, WIILIAM S. ORSER, do hereby af firm that the foregoing statenents are based on facts and circunstances which are true and accurate to the best of my knowledge and belief.
1
- WILIJAM S. ORSER Senior Vice President Cn this /7 _
day of u t44 .1990, before ne personally repeared William S. Orser/Jbeing first du',y sworn and says that he executed the foregoing As his free act and deoi.
fidb' Notary Public J/Xcicb
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Enclosura to
, .- NRC-90-0079 !
Page 1 INTRODUCTION l The Fermi 2 turbine generator, manufactured by the General Electric Company Turbine-Generator, Ltd. of Rugby, England, is a four-casing, tanden-compound, six-flow, 1800 rpm unit with 46 inch (nominal) last stago blades. An AC generator is connected to the turbine shaft. The ,
turbine consists of one double flow high pressure element in tanden with three double flow low pressure elements. The turbine generator bearings are lubricated by a conventional pressurized oil system. The turbine generator uses an electro-hydraulic control (EHC) system that controls the speed, load, pressure, and flow for startup and planned operation, and trips the unit in off-normal situations. The EHC system operates the high pressure stop and control valves, bypass l 1
valves, low pressure stop and intercept valves, and other protective l devices. Each valve is provided *:ith an individual unitized l actuator. The unitized actuators are self contained electro-hydraulic )
valve positioners that converi electrical control signals to valve I position. Steam from the nuclear steam supply systen enters the high l
- pressure turbine through four 24-inch stop valves each of which are in I series with a governing control valve. One stop valve and one control l
-valve form a single assembly. After expanding through the high i pressure turbine, the steam flows through the moisture separators and '
reheaters to the six intermediate stop valves each in series with an intercept valve into steam lines leading to the three low pressure turbines. Steam from each low pressure turbine is then exhausted into the main condenser. Moisture separation and reheating of the steam
, are provided between the high pressure and low pressure elements in ,
two parallel shells, each of which contains combined moisture separator reheater assemblies. A moisture separator reheater assembly i is located on ea::h side of the turbine parallel to the turbine shaft.
The turbine generator is protected from excessive overspeed by two ,
types of energency overspeed trip protection systems, the mechanical ;
overspeed trip systems and the electrical overspeed trip system. The overspeed protM tion systems are designed to prevent damage to the turbine and to equipment or structures from a turbine missile, i (Analyses of the turbine missiles concluded that they are most likely to occur from an overspeed condition.)
l The basis of the Standard Technical Specification 3/4 3 8 " Turbine Overspeed Protection System" involves maintaining the turbine overspeed protection system to reduce the hazards of turbine missiles. 'this function is discussed in Standard Review Plan Sections 3 5.1 3 and 10.2 3 However, based on the orientation and location of
,. the Fermi 2 turbine and the structural design of the plant, Detroit Edison has concluded that any potentially generated turbine missile will not prevent the reactor from achieving and maintaining a-safe -
shutdown condition. Please note that a turbine missile situation is highly dependent on the complete failure of all overspeed protection systems which is most improbable. Additionally, the Bases of TS 4
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U EnclosurO to NRC-90-0079 Page 2 3/4 3 8 states in part: " Protection from turbine excessive overspeed is not required to protect safety-related components, equipment, or structures. However, it is included in order to improve overall plant reliability." Therefore, Detroit Edison does not believe that the administrative controls imposed by the subject TS are necessary because a turbine missile will not prevent the reactor from achieving and maintaining a safe shutdown condition.
EVALUATION The removal of TS 3/4 3 8 from the Technical Specifications is based on the following items:
- 1) The turbine is protected from excessive overspeed by two types of emergency systems in addition to its normal speed control system.
- 2) Based on the orientation and location of Fermi 2 turbine and the structural design of the plant, any potentially generated turbine
' missile d il.not prevent the reactor from achieving and maintcining a safe shutdown condition.
- 3) Removing the subject TS would not require the plant to reduce power weekly to perform turbine valve testing associated with the overspeed protection systems. During transient operation (power increases and decreases) operational events are more likely to occur than operating at steady state conditions.
- 4) Recent.insoeotion of a sample of the turbine steam supply valves and the operational test history of the overspeed protection instrumentation indicate that this system has always remained operable.
- 5) The manufacturer's recommendations on turbine overspeed protection system testing and inspections will be followed to l ensure the reliability of the systems with consideration given to the operational constraints as a result of performing these tests and inspections.
l I s Each of the above items will be addressed below.
Loss of electrical load or malfunction of the control system can cause the turbine to overspeed. The mechanical and electrical emergency l'
overspeed protection systems operate to limit the maximum turbine speed under fault conditions. The mechanical overspeed trip function consists of M redundant systems using two separate spring-loaded eccentric rings mounted on the turbine shaft. When the turbine is accelerated to 110 to ill percent overspeed, each ring strikes its respective trip level which in turn moves a limit switch. Operation of either limit switch will energize a system of protective relays that will trip the turbine.
. - _ _ . . _ _ _ _ _ _ _ _ _ _ _ _ - _ _ _ _ _ _ - _ _ _ _ - _ _ _ A
j Encittura to NRC-90-0079 Page 3 The electrical overspeed system uses four separate and redundant channels of speed measurement. The four channels are fed through a network of comparative logic gates. This comparative logic system monitors the speed input signals and alerts the operator with an alarm if any one of the four inputs falls to match the others. Each channel energizes an overspeed trip relay (at 110% rated turbine speed) which has its output contacts arranged in two special two-out-of-four logic arrangements so that the operation of any two channels will trip the turbine. The two logic arrangements are arranged so that all six combinations of two channels are provided, although two combinations are duplicated. An output from either logic combination will trip the turbine. This design gives a high level of reliability with the minimum number of contacts. Spurious trips are avoided by this arrangement since each logic requires two channels to fail to the trip state before a turbine trip is initiated. Three channels must fail to l their non-trip state before the system becomes completely inoperative. The system's AC power supply is redundant with automatic throwover to a backup AC supply.
Both types of overspeed protection systems trip the turbine by closing all high pressure and low pressure steam supply valves. Each high and low pressure steam line to the turbine has two valves in series such that a failure of one valve in each steam line would not necessarily I cause a turbine to overspeed. Therefore, because of the redundancy 1 and diversity of the two types of emergency overspeed protection i systems the possibility of an overspeed condition occurring which l could potentially generate a turbine missile is extremely remote. l An analysL, performed in 1971 determined that the most likely source of a missile from the turbine generator is from wheel 8 of the .
low-pressure turbine. This analysis has indicated that other possible I missiles from the high-pressure turbine or the generator rotor would !
not penetrate their respective outer casing. The potential missile J from wheel 8 would be generated at an overspeed condition of 167 percent of rated turbine speed which is well above the overspeed protection systn s' trip setpoint of approximately 110 percent.
As stated above, the only missile which could possibly do damage to !
essential equipment would be a missile emanating from the low-pressure ,
section of the turbine (assuming the failure of all overspeed !
protection systems). This missile could break through the turbine casing in any radial direction. However, the direction of rotation of the turbine is such that the motion of the top half of the rotor ;
carries it away from the reactor and auxiliary buildings. !
Furthermore, these buildings are not in direct radial alignment with the low-pressure sections of the turbine. Thus, the possibility of the missile taking a direct horizontal path toward the reactor and auxiliary building is remote. If, however, the missile were directed horizontally toward the reactor as a result of an internal or external i
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NRC-90-0079 Page 4 collision its emerging translational energy would be absorbed and the missile stopped by the concrete shielding which surrounds the turbine. This shielding would be only partially penetrated by the missile with the missile surrendering all of its kinetic energy. 1
- Ancther path that the missile emanating from the low-pressure section of the turbine-generator could take is nearly vertically upwards through the roof of the turbine. It has been estimated that such a missile would lose very little energy penetrating the roof barrier.
This missile would have to be deflected elastically or acted upon by wind forces to give it a trajectory which would allow it to fall directly atop the reactor or auxiliary building. To protect against nearly vertical missiles, all missile barriers in the auxiliary and reactor building have the required thickness to stop turbine generated missiles and also prevent the generation of secondary missiles due to i concrete spalling and scabbing. !
The Fuel Storage Pool is not protected by a missJle barrier. However, j the~1971 analysis calculated that the probability of a missile ]
striking the fuel pool is less than once in every 10,000 years. j Detroit Edison concludes from this analysis that no turbine missile I i
will impact the fuel storage pool and thus no missile barrier is j required. ]
The above mentioned turbine missile analysis was performed prior to the design and construction of the RHR Complex. A more recent turbine missile analysis was performed for the RHR Complex. This analysis l concluded that a low trajectory missile (nearly horizontal) will be s
stopped by the turbine room's west wall. However, a vertically 8enerated missile could perforate the RHR Complex's roof and cause j
- equipment damage to one division. The RHR Complex houses two
! redundant safety-related divisions which are separated by a 4-ft thick L wall (see UFSAR Figure 3 5-2). This 4-ft thick wall is more than l, adequate to prevent any spalling or scabbing of concrete on the other L side (other division) of the wall and thus, will prevent any potential l missile from impacting more than one division. Therefore, in the unlikely event of a turbine missile impacting the RHR Complex roof at least one full division of equipment housed in the RHR Complex will remain OPERABLE to achieve and maintain a safe shutdown condition of the reactor. l l-L- Please note that the turbine missile analyses mentioned above have !
I been previously reviewed and accepted by the NRC as indicated in !
Reference 2, Section 3 5.2. Additionally, it was recognized that a potential turbine missile hazard was not the basis for Fermi 2 Overspeed Protection TS at the time of Fermi 2 licensing.
Accordingly, the subject TS Bases discusses the reliability benefits '
of maintaining the turbine overspeed protection system and not the need to maintain the system to reduce the hazards of turbine missiles.
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Enclosura to NRC-90-0079 Page 5 j
During the development of this proposal some inconsistencies were 1 identified in support documentation which were the basis for the I turbine, reactor and auxiliary building's turbine missile analysis and J UFSAR statements. Some of these support documents were also the basis 1 for Reference 2 conclusions. An evaluation of the inconsistencies and subsequent reanalysis of identified turbine missile barriers have determined that the conclusions and the factors of conservatisms as previously stated remain valid. However, some current UFSAR statements related to turbine missile protection are not accurate and are being changed, but these changes do not affect any conclusions .
previously made. In fact the same factor of conservatism or greater I has been verified. All turbine missile barriers in the turbine, reactor and auxiliary buildings have more than the vequired thickness for missile protection.
Technical Specification (TS) 3/4 3 8 requires that a weekly l surveillance requirement.be performed by cycling all turbine high pressure stop and control valves and all turbine low pressure stop and 1 intercept valves. In order to perform this surveillance requirement reactor power must be reduced to compensate for the reduction in steam l- flow to the turbine. This weekly reduction in reactor power is not desirable because of the capacity factor lossca and the associated transient operation (frequent power increases and decreases) of the ;
l p1hnt which makes it more susceptible to an operational event.
I L Recent inspections of some of the turbine's steam supply valves indicate that they are in good condition. During the first refueling outage two high pressure turbine steam supply valves were inspected.
No problems were identified on these valves. Additionally, the bearings and glands from two low pressure turbina valves were dismantled for inspection and found to be in gooa condition. The TS required testing of the mechanical and electrical overspeed protection l instrumentation has indicated that if a turbine overspeed condition had existed the turbine would have been tripped. At all times at least one mechanical system and enough channels of the electrical system were available to trip the turbine.
Detroit Edison intends to perform turbine overspeed protection system visuel inspections and testing in accordance with the manufacturer's recommendations with consideration given to the operational conctraints as a result of performing these inspections and tests.
Detroit Edison fully recognizes the benefit of performing these inspections and tests to ensure reliable operation of this station.
However, we do not believe that rigid Technical Specification requirements are needed on this system because as outlined above the postulated failure of this system and resultant proposed turbine missile will not prevent the reactor from achieving and maintaining a safe shutdown condition.
~
Enc 1ccure to 1 NRC-90-0079 Page 6 l NO SIGNIFICANT HAIARDS 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 evaluated, or 2) create the possibility of a new or different kind of accident from any accident i previously evaluated, or 3) involve a significant reduction in a margin of safety. ;
- 1) The proposed change does not involve a significant increase in the probability or consequences of an accide- previously evaluated because the turbine overspeed protection system is not required.to mitigate any design basis accident and the postulated failure of this system and resultant proposed turbine missile will not prevent the reactor from achieving and' maintaining a safe shutdown condition.. The basis for the subject system to be included in the Standard Technical Specifications is to reduce the hazards of turbine missiles. Turbine missiles from an !
overspeed condition at Fermi 2 are prevented by the two types of I emergency overspeed trip systems (mechanical and electrical) which trip redundant high and low pressure steam valves to prevent an overspeed condition. Analysis has determined that because of the orientation and location of the Fermi 2 turbine .
and the structural design of the plant, the effects of the worst case turbine missile will not prevent the reactor from achieving and maintaining a safe shutdown condition. Additionally, the proposed change would allow for less frequent power reductions for turbine valve testing. During these power reductions and subsequent power increases operational events are more probable than operation at steady state conditions. Therefore, the proposed change does not involve a significant increase in the probability or consequences of an accident previously evaluated I l
because the turbine overspeed protection system is not required to mitigate any design basis accidents and the postulated failure ,
of this system and resultant proposed turbine missile will not '
prevent the reactor from achieving and maintaining a safe !
shutdown condition.
- 2) The proposed change does not create tb possibility of a new or different kind of accident from any accident previously evaluated because the proposed change does not introduce a new mode of plant operation or involve a physical modification to the plant.
- 3) The proposed change does not involve v significant reduction in a margin of safety because, as outlined in item 1 above, the turbine overspeed protection system is not required to mitigate
Enclosure to NRC-90-0079 Page 7 any design basis accident and the postulated failure of this system and the resultant proposed turbine missile will not prevent the reactor from achieving and maintaining a safe shutdown condition. Additionally, the Bases of the subject TS states that the tur 1ne overspeed protection systems are included in the Fermi 2 TSs in order to " improve overall plant reliability". Plant and public protection from turbine missiles are ensured by the structural design of the plant and the orientation and location of the turbine, and not explicitly by the turbine's overspeed protection systems.
Based on the above, Detroit Edison has determined that the proposed amendment does not involve a signifseant hazards consideration.
ENVIROl003rfAL IMPACT Detroit Edison has reviewed the proposed Technical Specification changes against the criteria of 10CFR51.22 for environmental considerations. The proposed change does 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 the requiremerts 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 proposed amendments will not be inimical to the common defense and security or to the health and safety of the public.
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