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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
[Table view] |
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Decembe r 5,1991 .D NRC-91-0144 U. S. Huelcar Regulat ory Ccanaission Attnt Doctanent Conttol Der.k Washingt on. D. C. 20555
References:
- 1) Feral 2 NRC Docket No. 50-341 NRC License No. NPF-43
- 2) Det roit Edison let ter t o NRC. NRC-87-0244, dated Match 10, 1988
- 3) Detroit Edison let ter to NRC, NkC-89-0042, dated May 31, 1989
- 4) Dettoit Edison letter t o NRC NRC-89-0242, dated January 3,1990
- 5) Dottoit Edison letter to NRC. NRC-91-0080 dat ed July 2,1991
- 6) Detroit Edinon let ter to NRC, NRC-91-0156, dated November 27, 1991
- 7) Amendment 51 to Fe wi 2 Operating License NPF-43, dated February 20. 1990
- 8) Generic Letter 91-18 "Inf ormation to Licensees Regarding Two NRC Inspection Manual Sections on Resolution of Degraded and Nonconf orming Conditions and on Operability," dated November 7,1991
Subject:
Proposed Technical Specification Change (License ,
Amendment) - Emotgency Equipment Cooling Water and Emergncy Equipment Servi _ce Water Pursuant 'to 100FR50.90. Detroit Edison Company hereby proposes to amend Operating License NPF-43 for tho-Fermi 2 plant by incorporating the enclosed changes into the Plant Technical Specifications (TS).
The proposed change provides revised action requirements for the Emergency Equipment Cooling Water (EECW) and the Emergency Equipmt4nt Service Water ' (EESW) syst ems.- This submittal also proposes changes to the TS action requitements f or systems which receive EECW cooling where the supported system allowed outage time (A0T) is tnore g restrictive than the EECW AOT. These action requirements vote the o d)\
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tis!1RC December S.1991 1;RC-91-0144 Page 2 subject of previous ptopocals (Feferencer 2. 3 and 4). In Ecferenceo 5 and 6. Detroit Edison commit tal to provide a TS change proposal for EECW. Tbie proposal satisfies these cmmitment s.
Detroit Edison has evaluated the proposed Technical Specifications against the etiteria of 10CFR$0.92 and determined that no significant har.arda consideration is involved. The Femi 2 Onnit e Reviev Organir.ation has approved and the lluclear Safety Review Group has reviewed the proposed Technical Specificatiour and concurs with the enclored deter minat ions. In accordance with 10CFP50.91. Detr oit Edison han provided a copy of this letter to the State of Michigan.
If you have any questions, please contact Mr. Glen D. Ohlemacher at (313) 586-4275.
Since rel y.
7 Encionate cc C. E. Carpenter. Jr.
A. li. Davis R. W. DeFayette S. Stasek Supetvisor. Electric Operators. Michigan Public Service Cmmionion - J. R. Padget t
I USNRC NRC-91-0144 Tate 3 l
I. WILLI AM S. ORSER. do hereby af firm that the f otogoing statments are based on (acts and circumstaneen which are true and aceutate to the beat of ny knowledge and belief.
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f/ ( ( /$Y-WILLI AM S. ORSP.R
' Il'lk' Senior Vice President On this I day of _I #fffd/ ( _. 1991, b fore me personally appeared William S. Orcer, being if rut duly sworn and says that he executed the foregol.ng as his f ree act and deed.
l J ,1l'$c. If- l//L* W '
Notaty Public E Anygyg
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Enclosure to NRC-91-0144 Page 1 INTRODUCTION The proposed TS change is being made to reconcilf, the TS required actions for the Emergency Equipment Cooling Water (EECW) and Emergency Equipment Service Water (CESW) systems and the TS required actions for certain systems which recolve EFCW/EESW cooling. These systems are the Emergency Core Cooling Systems (ECCS), the A.C. electrical distribution, and the battery chargers. In each system, the TS required action for the inoperability of the EECW/EESW supported equipment is more limiting than the required action for an EECW/EESW subsystem inoperability.
The need to reconcile these TS actions came from the issuance of Generic Letter (CL) 91-18, (Reference-8) which distributed an NRC Inspection Manual, Part 9900 Section on the topic of operability.
This section indicated that when the TS required action for a support system is less restrictive-than a TS required action for a supported system then the nost restrictive action should be followed until the inconsistencies are resolved. The section also indicates that an amendment to the TS may be necessary.
Previous to the issuance of C1 91-18, Detroit Edison had identified this inconsistency between the EECW/EESW action requirements and the action requirements of the supported systems. While resolving the inconsistency with the NRC, addillonal actions, such as checks of opposite train equipment to assure that complete loss of a safety _ ,
function did not occur, were implemented, liowever, the most restrictive actions from tha supported system TS requirements were not taken since these actions did not appear warranted by the safety significance of the situallon nor intended by the TS and original licensing basis. Discussions with NRC representatives since the issuance of GL 91-18 made it clear that the most restrictive actions should be taken immediately upon loss of EECW cooling and that a license amendment would be required to resolve tnis attuation.
Detroit Edison does not believe that this was the intent of the original EECW/EESW action requirements and is in support of the ,
ongoing dialog between industry owners' groups and the NRC toircach a generio position on this issue. Prompt resolution of the EECW/EESW action requirements, however, is needed to support continued plant operation, necessary' surveillance testing and preventive maintenance on these systems.
Detroit Edison is electing to resolve this issue, at least for the near future, by proposing a TS change where the systems supported by EECW would be immediately declared inoperable and the associated TS actions are directed to be taken. Certain of these supported systems' TS requirements are also proposed to be modified to specifically address the degradation caused by the loss of EECW cooling.
i i
I Enclosure to NitC-91-0144 Pago 2 1 EVM UATION The Emergency Equipment Cooling Water (EECW) system provides cooling to equipment essent,tal to reactor shutdown wnenever the normal cooling to this equipnent is unavailablo. The Emergency Equipment Servlee Water (EESW) system provides cooling to the 1:CCW system and is in turn cooled by the Ultimato llcal Sink. The sole function of the EESW system is to cool the EECW system.
The EECW and EESW systems each consist of two subsystemn. The subsystems are independent, and divisionalized. The essential safety-related equipment, supported by EECW la an follows:
o Itesidual llent itemoval (Illilt) Pumps o Coro Spray (CS) Pumps o Non-interruptiblo Control Air Compressors o Thermal Recombiner System o Electrical Switchgear '
o Henetor Coro isolation Cooling (11C10) o liigh Pressuro Coolant, injection (llPCI) o Standby Cas Treatment Syst.em o- Control Room Emergency Filtration System o Essent,lal Battery Chargers Heat. removal from this equipment. la normally via the non-safety related Reactor Building Closed Cooling Water (ItBCCW) system. The t,wo EECW nystem subsystems are in ofrect two branches in the distritsution of RBCCW system cooling water. In the event, of an EECW initiat,lon signal (loss of IWCCW supply pressura, loss of power to the HBCCW pumps or high drywell pressure) the !!DCCW system valves are automat,1cally repositioned to form the two independent, EECW subsystems. The RDCCW pumps and heat, exchangers are isolated from the EECW subsystems, and the EECW pumps roccivo a start signal. A simplified sketch is attached. The EECW/EESW system design was reviewed and accepted by the NHC in tho Fermi 2 Safety Evaluation Report (NUREG-0798), Section 9.2.1.
The current TS requirements for EECW (TS 3 7.1.2) and EESW (TS 3 7.13) provide for a 72 hour8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> allowed outage timo ( AoT) for loss or one subsystem. After the 72 hour8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> A0T expires, a plant shutdown is required, the associated safety-relat,ed equipment is t,o be declared inoperable and the applicable action requirements for the supported equipment, followed.
This TS action creates severni problems. First, the use of the 72 hour8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> ACT is not appropriato in situaiaons where an opposite train component, which N "ellant, on the remaining operable EECW subsystem, is also inoperable. In this case, the safety function may be lost, and a more restrictive action requirement should be applied. The proposed TM addresses this issue by requiring a verification of opposito train 1
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Enclosure to llRC-91-0144 Page 3 equipment within two hours, which if not completed, requires a prompt plant shutdown.
This is consistent with the guiding principle, expressed in GL 91-18.
that the capability to perform a safety function must not be lost due to inoperabilities in nore than one train. Requiring a plant shutdown if a safety function is lost is consistent with the TS actions for these functions. An exception la made for the alternative shutdown system where the TS provides an appropriate action statement for less of both trains of the EECW supportej drywell cooling units.
The second problem is that the operability status of plant equipment should reflect the physical state of the equipnent. The current TS provision could lead to the conclusion that it is acceptable to consider inoperable equipment operable during a 72 hour8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> A0T. This is inconsistent with both the operability definition and ino actual status of the equipment. Therefore, the proposed "5 requires that associated safety-related equipment nade inoperable by loss of EECW cooling be declared inoperable at the time cooling is lost.
The proposed TS then directs that the action requirements for the supported systems be taken. This is the clearest way of assuring that the necessary action requirements (including any remedial actions) are taken. Since the supported system TS requirements were not written to take into account a loss of EECW cooling, certain supported system TS must be changed. These systems are the ECCS, A.C. electrical distribution and the battery chargers.
The Fermi 2 Emerf,ency Core Cooling System (ECCS) network consists of a standard BWR-4 design consisting of a Low Pressure Coolant Injection <
(LPCI) system, a Core Spray System (CSS), a High Pressure Coolant injection (HPCI) system and an Automatic Depressurization System (ADS). The I.PCI systems and CSS consist of two redundaac subsystems.
The HPCI system and ADS provide redundant function *.
The TS actions for the ECCS allow one of the six systems or subsystems, detailed above, to be inoperable for time periods of seven (7) through fourteen (14) days. The time periods reflect the defense in depth of the ECCS network. Circumstances where more than one system / subsystem would be simultaneously inoperable were considered to be unlikely when the TS were drafted. Therefore, actions with shorter A0Ts were not included in the original TS.
Loss of the Division II EECW subsystem results in the inoperability of the Division II LPCI and CSS subsystems and the HPCI system. Loss of the Division I EECW system results in inoperability of the Division 1 LPCI and CSS subsystems. ADS is not affected by a loss of EECW.
The current ECCS TS actions (TS 3 5.1) do not cover the resulting ECCS inoperabilities for the situation when an EECW subsystem is
'o ., i Enclosure to NRC 91-0144 j Page 4 j i
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inoperable. TS 3.5 1 does not contain an action stat.cment that addresses the multiple subsystem inoperabilities which result. l Therefore, entry into TS 3 0 3 and an immediato plant, shutdown is i j
required. Tha proposed TS changes overcomo this problem by including a provision which addresses loss of an EECW subsystem within the TS j E 3 5.1. actions.
The exJsting evaluation in the UFSAR of a failure of a divisional battery provides a conservative evaluation of the impact on the ECCS of a loss of that division of EECW. The battery failure causes the control power to motor-operated valves for the ECCS within the affected division to be lost not allowing the ECCS in that division to operate. This bounds the EECW case where the ECCS in a division would operate but be subject to subsequent failuro duo to loss of cooling.
The ECCS performance evaluation (UFSAR Section 6.3 3) or the divisional battery failure shows that all ECCS acceptance critoria of 10CFR50.46 are met. The results are displayed in UFSAR Figure 6 3-17 These evaluations have been reviewed and accepted by the NRC in the Fermi 2 SER, Section 6.3 4.
The proposed changes to TS 3 6.1 provido directions which result, in the 72 hour8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> A0T of the EECW TS being limiting when loss of EECW cooling requires entry into 3 5.1. The cross-train checks, discussed above, assure that sufficient, equipment remains operable to meet the ECCS functional requirements.
The EECW system also supports the A.C. electrical distribution equipment and the bat,tery chargers. The current TS A0Ts for loss of one division of these syst. ems are 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> and 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />, respectively.
!!owever, these A0Ts do not reflect the capability of this equipment under accident conditions without EECW cooling.
The EECW supports the A.C. electrical distribution system by cooling the rooms in which the equipment is located. These rooms are
' maintained by non-safety air conditioning systems at less than ,
86 0F, This temperature is chosen to prevent accelerated aging of electronic' components in the room. The room equipment. Will function l
properly with temperatures up to'122 F.
l An evaluation of room temperature versus time has shown that post-accident without EECW cooling the room temperature increases from 86U F to 1220 F in 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> and 24 minutes for Division Il and 10 i
hours and 2 minutes for Division I. The non-safety air conditioning is assumed to fail at, the time of the accident.
The battery charEers are similarly supported by EECW; however, the room temperature increases much less rapidly than for the A.C.
electrical distribution. Since the battery chargers require an A.C.
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Enclosure to NRC-91-0144 Page 5 power supply, the battery chargers' capability wl.thout EECW is limited by-the A.C. electrical distribution capability.
The propoLed TS allows the action requirements for this equipment to be delayed La reflect this post-accident. capabilit,y. Since the systems retain their full capability for a period of t,ime following an accident it wtuld appear to be appropriate to 6110w a time period of at least.this long for a delay in taking these action requirements.
Therefore, a delay of 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> for Division 11.and 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> for Division I is proposed for these actions. Thhse delay times are based upon conservative calculations which are curmntly being refined.
Should the revised cal.uulations support appreciably longer delays, Detroit Edison may supplement this proposal to reflect the longer delays, t In Operational Condition 4 and 5, there is no need to consider cont.inued plant operation. The incent is to take the action for any equipment which is rendered inoperable by the loss of EECW cooling.
Whether or not a piece of equipment should be considered inoperable depends upon the impact of the loss of ECCW on the equipment's ability to perform its intended function. In Operational Conditions 4 or 5, the need for-EEGW cooling may depend upon the design basis scenarios which can credibly. occur in these conditions. Thus, there could be no actual impact on the equipment's ability to perform its intended
. function with a loss of EECW cooling. For example, some EECW cooled room coolers may not be netded under accident conditions when the reactor is at low temperatures. The equipment in these rooms thus would still be-able to fully perform its intended functions and would not naed to be declared fi,uperable.
The EECW system is designed ,,a provide cooling to-equipment essential to achieving and maintaining safe shutdown conditions under postulated accident conditions. The worst-case conditions are generally those following an accident originating 'derring power operat. tan. There are a number of specific circumstances possible in Operational Conditions 4 and-5 for which the worst-case conditions are substantially less severe tnan those possible at power. Engineering evaluation of each l: specif4?. circumstance-may result in a determination that the equipment l .of cc m rn can be considered operable. The proposed action b. of TS
- 3 7.1.2 reflects the intended action without mixing the Operational Conditions 4 and 5 requirements with the more complex Operational' Condition 1, 2 and 3 requirements.
h In License Amendment'51 (Reference 7) the Ultimate Heat Sink TS (3 7.1.5) was changed to refer only to equipment or systems which are directly supported by the Ultimate Heat Sink. This proposal continues
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-that philosophy for EESW in that the proposed EESW TS requires the f,ECW action to be taken. EESW cools only the EECW system. Thus, restructuring of the action alone does not in itself change the requirements from the current Technical Specification requirements.
Enclosure to NRC-91-0144 Fege 6 The proposed restruct ring still requires the same actions for an EESW inoperability as for an EECW Inoperability but eliminates duplication of the EECW requirements. The proposed structure also supports a more systematic evaluation of the impact of the inoperability of this system. In this way, the proposal provides a clear and simple format for these requirements while ensuring the proper actions for the supported systems are taken.
In tummary, these TS changes act to eliminate any potential conflict between the explicit TS actions for EECW nd the application of tne operability definition to the suppcrte ett m TS.
When the most restrictive. V' Os are % , sied, as ceacribed in GL 91-18, EECW/EESW systen outages are essentially prohibited since such an outage would cause entry into the TS 3.0 3 provisions. System outages for these systems are periodically necessary to allow for surveillance testing activities and minor preventir maintenance to be performed. Such activities act to enhance these systems' reliability and availability and thus act to benefit safety. The proposed chandes are consistent with the intent of CL 91-18 which indicates that it "is not the intent of surveillance or other similar program requirements to cause unwarranted plant shutdowns..."
Also, when the most aestrictive action requirements of the current TS's are immediately 0.pplied they give no allowance for tinor corrective maintemnce on the EECW/EESW systems. These corrective maintenance items currently would require a plant shutdown where an adequate safety basis exists for ACT's sufficient to accommodate them. These unwarranted plant shutdowns would place unnecessary cycles on plant equipment. These plant evolutions also craate a greater probability of an abnormal plant transient being initiated due to the increased activity during the evolutions. Eliminating these plant shutdowns is a safety benefit.
SIGNIFICANT llAZARCS 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 th".t operation in accordance with the p-oposed 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 pre.iously evaluated, or 3) involve a significant reduction in a margin of safety.
The proposed change provides revised action requirements for the Emergency Equipment Cooling Water (EECW) system, Emergency Equipment Service Water (EESW) system and certain systems which receive EECW cooling. The change requires additional actions to be taken for an
Enclosure to NRC-91-0144 Page 7 inoperable EECW subsystem to ensure a loss of safety function has not occurred and directs that the action requirements for systems made inoperable by the loss of EECW cooling be immediately taken. Certain of the supported system action requirements are changed to reflect the impact er loss of EECW cooling on the supported equipment. The proposed change does not:
- 1) Involve a significant increase in the probability or consequences of an accident previously evaluated. The proposed change does not create any new initiating mechanisms or affect any postulated initiating mechanisms for evaluated accidents. The proposed change provides action requirements that. address the impact of EECW cooling on certain systems which receive EECW cooling.
These action requirements assure that sufficient equipment remains available to safely shutdown the plant as currently evaluated in the UFSAR. The UFSAR evaluation of ECCS performance shows that equipment supported by a single EECW subsystem can meet the acceptance criteria of 10CFR50.46. Therefore, the proposed change does not represent a stEnificant irrrease in the probability or consequences of a previously evaluated accident.
- 2) Create the possibility of a new or different kind of accident from any accident previously evaluated. The proposed change does not result in any modifications to the plant design or manner of system operation and no safety-related equipment or function will be altered. As stated in 1) above, sufficient equipment will be maintained and will be available to initiate safe shutdown of the plant. The requested changes do not create any new accident mode.
- 3) Involve a significant reduction in a margin of safety. As stated in 1) above, the proposed action requirements assure that sufficient equipment is available to safely shutdown the plant.
The proposed change nay also promote safe plant operation by giving a reasonable out-of-service time for corrective and preventive maintenance and testing activities on the EECW and EESW systems without requiring unnecessary reactor shutdowns.
Based on the above, Detroit Edison has determined that the proposed amendment does not involve a significant hazards consideration.
ENVIRONMENTAL 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 r adiation exposures. Based on the foregoing, Detroit
Enclosure to NRC-91-0144 ,
Page 8 Edison colicludes that the proposed Technical Specifications do meet the criteria given in 10CFR51.22(c)(9) for a categorical exclusion from the requirements 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 proposed amendments will not be inimical to the common defense and security or to the health and safety of the public.
In order to provide time for the revision of site docutients, it is requested that the proposed change be issued with a seven day implementation period, l
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