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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] |
Text
.
j' ~
Douglas R. Gipson
. Scrwe Vnv Present
%*ar Generwon Detroit r-Ec ison - a.s<wouw*uy na %w-Hay 10, 1994 NRC-94-0047 U. S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, D.C. 20555
References:
- 1) Fermi 2 NRC Docket No. 50-341 NRC License No. NPF-43
- 2) Generic Letter (GL) 91-08, " Removal of Component Lists from Technical Specifications," dated May 6, 1991
Subject:
Proposed Technical Specification Change (License Amendment) Removal of Component Lists from Technical Specifications Pursuant to 10CFR50.90, Detroit Edison Company hereby proposes to amend Operating License NPF-43 for the Fermi 2 plant by incorporating the enclosed changes into the Plant Technical Specifications (TS).
The proposed changes removes the component lists from TS Sections 3.6.3 (Table 3.6 3-1, Primary Containment Isolation Valves) and 3.8.4 3 (Table 3 8.4.3-1, Motor-Operated valves Thermal Overload Protection) in accordance with the guidance set forth in NRC Generic Letter 91-08 (Reference 2). In addition to removing the subject component lists, this proposed amendment modifies portions of the TS that specifically reference these lists. .The lists removed from the TS will be incorporated into plant procedures subject to the administrative controls of TS 6.5.3 and 6.8. This modification is a line item TS improvement as described in Reference 2.
Detroit Edison has evaluated the proposed TS against the criteria of 10CFR50.92 and determined that no significant hazards consideration is involved. The Fermi 2 Onsite Review Organization has approved and the Nuclear Safety Review Group has reviewed the proposed TS and concurs with the enclosed determinations. In accordance with 10CFR50.91, Detroit Edison has provided a copy of this letter to the State of Michigan.
9405160127 940510 PDR P
ADOCK 05000341 PDR -(\ j
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USNRC
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May 10, 1994 NRC-94-0047 Page 2 Additionally, Detroit Edison is expected to save over $200,000 over the remaining plant' lifetime if this TS change is approved.
Furthermore, if this TS change is approved it will prevent Detroit -
Edison from having to submit at least one additional component list TS change- for NRC approval prior to startup from the present extended outage. Consequently, the proposed change is being requested to coincide with the present refueling outage (RF04) and Detroit Edison requests that it be approved by July 15, 1994. t A summary of the proposed changes, an Evaluation, the Significant Hazards.and Environmental Impact Considerations and a Conclusion are provided in Attachment 1. Attachment 2 provides a copy of the proposed TS changes.
If you have any questions, please contact Mr. Glen D. Ohlemacher at (313) 586-4275 Sincerely, g M Enclosures cc: T. G. Colburn J. B.' Martin M. P. Phillips K. R. Riemer Supervisor, Electric Operators, Michigan Public Service Commission - J. R. Padgett I'
n - ,
z 1
L USNRC May 10, 1994 NRC-94-0047 Page 3 i
I I
I l
I, DOUGLAS R. GIPSON, do hereby affirm that the foregoing statements are based on facts and circumstances which are true and l accurate to the best of my knowledge and belief. I DOUGLAS k. GIPSON Senior Vice President 4
On this /8 day of < 4tV , 1994 before me personally appeared Douglas R. Gipsoh, geing first duly sworn and says that he executed the foregoing as(his free act and deed.
4M la k. 41 Notary Public '
ROMUE A ARAEITA
- NOTARY PUBUC STATE ONQ9CAN NONROE COUNTY My cr56.4tWON EXP. NOV. 20,1995 4
ATTACIIMENT 1 PROPOSED TECIINICAL SPECIFICATION CIIANGE (LICENSE AMENDMENT)
RDIOVAL OF COMPONENT LISTS FROM TECIINICAL SPECIFICATIONS 1
l 4 -- m ,--
Attachment I to NRC-94-0047 Page 1 of 12 INTRODUCTION The Nuclear Regulatory Commission (NRC) issued Generic Letter (GL) 91-08, " Removal of Component Lists from Technical Specifications," on May 6,1991. This GL provides 4 guidance for preparing a request for a license amendment to relocate component lists from Technical Specifications (TS) into plant procedures. This guidance included incorporating the component lists into plant procedures that are subject to the change control provisions in the Administrative Controls Section of the TS, This will provide an acceptable alternative to identifying every component by its plant identification number as it is currently listed in the TS Tables. The change contml provisions of the TS provide an adequate means of contmiling changes to these component lists, without including them in the TS. The removal of these component lists is acceptable because it does not alter existing TS requirements or those components to which they apply. The nuclear industry and the NRC identified this line-item ,
TS improvement during investigations of TS concerns.
Detroit Edison proposes to relocate the component lists of TS Tables 3.6.3-1 (Primary Containment Isolation Valves) and 3.8.4.3-1 (Motor-Operated Valves Thermal Overload Protection) to plant procedures, in accordance with the guidelines provided by GL 91-08.
These component lists will then be subject to the procedure change control provisions contained in the Fermi 2 TS Sections 6.5.3 and 6.8, which are subsections of the TS Administmtive Controls Section (6.0). In addition to removing the subject component lists, this proposed amendment will modify portions of the TS that specifically reference these lists.
The plant procedures, that the TS component lists are being relocated to, will include all-components and applicable footnotes currently listed in the TS. The operability requirements for components being relocated (e.g., LIMITING CONDITION FOR OPERATION, APPLICABILITY, ACTION and SURVEILLANCE REQUIREMENTS) remain in the TS.
l In accordance with Generic Letter 91-08, the following changes to the TS am being proposed.
The changes are described in the order in which the associated TS appears in the Technical Specifications.
- 1. TS INDEX
- a. The index is being revised to make editorial corrections to reflect the deletion of TS Tables 3.6.3-1 and 3.8.4.3-1, which contain component lists as described below. The proposed TS page changes are attached. They are prepared in accordance with the guidance in Reference 2 .
I
Attachment I to NRC-94-0047 Page 2 of 12
- 2. DEFINITIONS
- a. Revise section a.2 of Definition 1.29, PRIMARY CO'NTAINMENT ,
INTEGRITY, to delete reference to table 3.6.3-1 and to denote the following:
" Closed by at least one manual valve, blank flange, or deactivated automatic valve secured in its closed position, except for valves that are open under administmtive control as pennitted by Specification 3.6.3. "
Section a.2 of Definition 1.29, PRIMARY CONTAINMENT INTEGRITY is proposed to be revised to delete the reference to Table 3.6.3-1 (Primary Containment Isolation Valves) and the Definition wording is mvised accordingly. The referenced Table 3.6.3-1 is being deleted from the TS and >
relocated to plant procedures. The list of primary containment isolation valves is not necessary to support the actions or surveillances required by the TS. The proposed word changes are consistent with the guidance provided in GL 91-08.
- 3. ISOLATION ACTUATION INSTRUMENTATION (3/4.3.2)
- a. Delete the column " Valve Gmups Operated By Signal" in Table 3.3.2-1, delete Table 3.3.2-1, Table Notations (d), (c) and (j); and relocate (as specified below)
Table 3.3.2-1, Table Notations (***), (f) and (g) associated with the valve groups.
Table 3.3.2-1 includes information on the " VALVE GROUPS OPERATED BY SIGNAL." This information identifies the valve group by each isolation trip function and includes a number of notes which are associated with the trip ;
function or the valve groups. Specifically, the valve groups are proposed to be deleted from the TS and relocated to plant procedures. The valve gmups identified in this TS are for infonnation only and require a listing of the individual valves (associated with the groups) to be of use. The curmnt listing of individual valves (associated with the gmups) is currently provided in Table 3.6.3-1 (Primary Containment Isolation Valves). Table 3.6.3-1 is also being deleted fmm the TS and relocated to plant procedures. The valve groups are not necessary to support the actions or surveillances required by the TS.
The footnotes associated with Table 3.3.2-1 will be distributed as described telow:
Attachment I to NRC-94-0047 -
Page 3 of 12 ROTE NEW LOCATION Retain as is in TS Retain as is in TS Relocate with valve group infonnation to plant procedures and retain in TS - Relocate footnote under Trip Function column in Table 3.3.2-1 (a) Retain as is in TS (b) Retain as is in TS (c) Retain as is in TS (d) Relocate with valve group infonnation to plant procedures and delete in TS (e) Relocate with valve group infonnation to plant pmcedures and delete in TS (f) Relocate with valve group infornution to plant procedures and retain in TS - Relocate footr.ote under Trip Function column in Table 3.3.2-1 (g) Relocate with valve group information to plant procedures and retain in TS - Relocate footnote under Trip Function column in Table 3.3.2-1 (h) Retain as is in TS (i) Retain as is in TS (j) Relocate with valve group infonnation to plant procedures and delete in TS Identified changes to the infonnation being relocated to plant procedures will continue to be controlled and reviewed in accordance with TS Sections 6.5.3 and 6.8, which are subsections of the TS Administrative Controls Section (6.0), As a result, the deletion and subsequent relocation of this infonnation from the TS
r Attachment I to NRC-94-0047 Page 4 of 12 complies with the guidance contained in GL 91-08. The proposed change, therefore, does not result in a technical change to the TS.
- b. Delete Footnote (#) in Table 3.3.2-3.
Table 3.3.2-3, Footnote (#), is proposed to be deleted sinc 3 it refemnces Table 3.6.3-1 (Primary Containment Isolation Valves) and valve groups. Specifically, the valve groups are proposed to be deleted from the TS and relocated to plant procedures. The valve groups identified in this TS are for information only and require a listing of the individual valves (associated with the groups) to be of use.
The current listing of individual valves (associated with the groups) is currently provided in Table 3.6.3-1 (Primary Containment Isolation Valves). Table 3.6.3-1 is also being deleted from the TS and relocated to plant procedures. The valve groups are not necessary to support the actions or surveillances required by the TS.
Table 3.6.3-1. The reference to the tables and the valve groups is for information only and is not necessary to support the actions or surveillances requimd by the TS.
Additionally, Isolation System Response Time is adequately defined in TS 1.16, therefore the (#) note in Table 3.3.2-3 is only infonnational. Also, Detroit Edison has submitted a TS change to remove all response time tables from the TS in accordance with GL 93-08. These response time tables will be relocated to the UFSAR..
- 4. PRIMARY CONTAINMENT INTEGRITY (3/4.6.1)
- a. Revise SR 4.6.1.1.b to delete reference to Table 3.6.3-1 and to denote the following:
" At least once per 31 days by verifying that all primary containment penetrations except those inside the containment or in locked high radiation areas (listed in Table 4.6.1.1-1) not capable of being closed by OPERABLE containment automatic isolation valves and required to be closed during accident conditions are closed by locked closed valves, blank Ranges, or deactivated automatic valves secured in position, except for valves that are open under administrative control as permitted by Specification 3.6.3. "
l SR 4.6.1.1.b is proposed to be revised to delete the reference to Table 3.6.3-1 l (Primary Containment Isolation Valves) and the SR wording is revised )
accordingly. The referenced Table 3.6.3-1 is being deleted from the TS and j relocated to plant procedures. The list of primary containment isolation valves 1 is not necessary to support the actions or surveillances required by the TS. The !
proposed word changes are consistent with the guidance provided in GL 91-08.
1 I
l
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Attachment 1 to NRC-94-0047 Page 5 of 12 l
- 5. PRIMARY CONTAINMENT LEAKAGE (3/4.6.1)
- a. Revise LCO 3.6.1.2.b to delete reference to Table 3.6.3-1 and to denote the following:
"A combined leakage rate of less than or equal to 0.60 La for all primag i containment penetrations and all primary containment isolation valves, except ,
for main steam line isolation valves
- and primay containment isolation valves l which are hydrostatically tested, subject to Type B and C tests when pressurized l to Pa, 56.5 psig."
LCO 3.6.1.2.b is proposed to be revised to delete the reference to Table 3.6.3-1 (Primary Containment Isolation Valves) and the LCO wording is mvised accordingly.
The referenced Table 3.6.3-1 is being deleted from the TS and relocated to plant procedures. The list of primary containment isolation valves is not necessary to support the actions or surveillances required by the TS. The proposed word changes !
are consistent with the guidance provided in GL 91-08.
- b. Revise ACTION Statement (with) 3.6.1.2.b, and ACTION Statement (restore) 3.6.1.2.b to delete mferences to Table 3.6.3-1 and to denote the following, respectively:
ACTION Statement 3.6.1.2.b: l WITH " The measured combined leakage rate for all primary containment penetrations and all primary containment isolation valves, except for main steam line isolation valves
- and primary containment isolation i valves which are hydrostatically tested, subject to Type B and C tests exceeding 0.60 La ,or "
l RESTORE " The combined leakage rate for all primary containment penetrations and all primary containment isolation valves, except for main steam line isolation valves
- and primary containment isolation valves which are .l hydrostatically tested, subject to Type B and C tests to less than or equal l to 0.60 La, and "
i l
ACTION Statement (with) 3.6.1.2.b, and ACTION Statement (restom) 3.6.1.2.b are l proposed to be revised to delete the references to Table 3 6.3-1 (Primary Containment !
Isolation Valves) and the ACTION Statement wording is revised accordingly. The l referenced Table 3.6.3-1 is being deleted from the TS and relocated to plant procedures. The details in this table are not necessary to support the actions or ;
l
Attachment I to N~RC-94-0047 Page 6 of 12 surveillances required by the TS. The proposed word changes are consistent with the guidance provided in GL 91-08.
- c. Revise footnote (*) for SR 4.6.1.2.b to remove the reference to Table 3.6.3-1 and to denote the following:
" *Unless a hydrostatic test is required."
Footnote (*) associated with SR 4.6.1.2.b is proposed to be revised to delete the reference to Table 3.6.3-1 (Primary Containment Isolation Valves). The referenced Table 3.6.3-1 is being deleted from the TS and relocated to plant procedures. The details in this table are not necessary to support the actions or surveillances required by the TS. The proposed word changes are consistent with the guidance provided in GL 91-08.
- d. Added footnote (#) for SR 4.6.1.2.b to denote the following:
" # Except for LPCI I. cop A and B Injection Isolation Valves, which are hydrostatically tested in accordance with SpeciGcation 4.4.3.2.2 in lieu of this requirement."
Footnote (#) is proposed to be added to SR 4.6.1.2. since Table 3.6.3-1 (Primary Containment Isolation Valves) is being deleted. Table 3.6.3-1 effectively addressed this issue with footnote (s). However, because the table is being deleted, footnote (s) will also be deleted. Therefore, the (#) footnote was added to SR 4.6.1.2 to clarify the hydrostatic testing of LPCI Loop A and B Injection Isolation Valves Ell-F015A and El1-F015B. The proposed worti changes are consistent with the guidance provided in GL 91-08.
- 6. PRIMARY CONTAINMENT ISOLATION VALVES (3/4.6.3)
- a. Revise LCO 3.6.3 to delete reference to Table 3.6.3-1 and the reference to isolation times shown in Table 3.6.31 as denoted by the following:
"Stch primary containment isolation valve and reactor instmmentation line excess flow check valve hLall be OPERABLE.**"
LCO 3.6.3 is proposed to be revised to delete the reference to Table 3.6.3-1 (Primary Containment Isolation Valves). The referenced Table 3.6.3 denotes primary containment isolation valves and associated isolation times.
The table is being deleted from the TS and relocated to the plant procedures.
The list of primary containment isolation valves is not necessary to support P
Attachment I to
- NRC-94-0047 Page 7 of 12 the actions or surveillances required by the TS. The footnote (**) was also added to the LCO as per the guidance in GL 91-08. The new footnote reads as follows: " ** Locked or sealed closed valves may be opened on an intermittent basis under administrative control. " The proposed word changes are consistent with the guidance provided in GL 91-08.
- b. Revise ACTION Statements 3.6.3.a aud 3.6.3.b and SR 4.6.3.1, SR 4.6.3.2, SR 4.6.3.3, and SR 4.6.3.4 to delete references to Table 3.6.3-1 and to denote ;
the following, respectively:
ACTION Statement 3.6.3.a; "With one.or more of the primary containment isolation valves inoperable, maintain at least one isolation valve OPERABLE in each affected penetration that is open and within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> either:"
ACTION Statement 3.6.3.b:
" With one or more of the reactor instrumentation line excess flow check valves inoperable, operation may continue and the provisions of Specification 3.0.3 are not applicable provided that within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> either: "
i SR 4.6.3.1:
" Each primary containment isolation valve shall be demonstrated OPERABLE prior to returning the valve to service after maintenance, repair or replacement work is performed on the valve or its associated actuator, control or power circuit by cycling the valve through at least one complete cycle of full travel and verifying the isolation time.*"
SR 4.6.3.2:
" Each primary containment automatic isolation valve shall be demonstrated OPERABLE during COLD SHUTDOWN or REFUELING at least once per 18 months by verifying that on a containment isolation test signal each automatic isolation valve actuates to its isolation position. " ,
SR 4.6.3.3:
" The isolation time of each primary containment power operated or automatic valve shall be determined to be within its limit when tested pursuant to Specification 4.0.5. "
Attachment 1 to NRC-94-0047 Page 8 of 12 SR 4.6.3.4:
" Each reactor instmmentation line excess flow check valve shall be demonstrated OPERABLE at least once per 18 months by verifying that the valve checks flow. "
ACTION Statements 3.6.3.a and 3.6.3.b and SR 4.6.3.1, SR 4.6.3.2, SR 4.6.3.3, and SR 4.6.3.4 are pmposed to be mvised to delete the mference to Table 3.6.3-1 (Primary Containment Isolation Valves). The referenced Table 3.6.3-1 is being deleted from the TS and relocated to the plant procedures. The details in this table are not necessary to support the actions or surveillances required by the TS.
- c. Revise SR 4.6.3.1 to delete the word "specified" and to denote the following:
"Each primary containment isolation valve shall be demonstrated OPERABLE prior to returning the valve to service after maintenance, repair or replacement work is performed on the valve or its associated actuator, control or power circuit by cycling the valve through at least one complete cycle of full tmvel and verifying the isolation time" The
- at the end of SR 4.6.3.1 will also remain. It signifies a footnote which states, " Except for TIP shear valves which are demonstated OPERABLE per Specification 4.6.3.5."
SR 4.6.3.1 is proposed to be revised to delete the word "specified" since, with the deletion of Table 3.6.3-1 (Primary Containment Isolation Valves), the isolation times for primary containment isolation valves are no longer specified.
Table 3.6.3-1 is being deleted from the TS and relocated to the plant procedures. The reference to the isolation times are not necessary to support the actions or surveillances required by the TS.
- d. Delete Table 3.6.3-1, " Primary Containment Isolation Valves" and retain a single page with the following note: "3/4 6-22 through 3/4 6-47 are 'not used'," which will account for the skipped pages.
Table 3.6.3-1 is pmposed to be deleted from the TS and relocated to plant procedures. Table 3.6.3-1 currently denotes primary containment isolation valves associated with Specification 3/4.3.2 (Isolation Actuation Instmmentation), Specification 3/4.6.1.1 (Primary Containment Integrity),
Specification 3/4.6.1.2 (Primary Containment Leakage) and Specification
Attachment I to NRC-94-0047 Page 9 of 12 3/4.6.3 (Primary Containment Isolation Valves). The table also consists of a list of associated valve numbers and maximum isolation times. The footnotes associated with Table 3.6.3-1 are also proposed to be relocated to plant procedums. The footnotes in this table are for information only. The list of primary containment isolation valves is not necessary to support the actions or surveillances required by the TS. The information being relocated to plant procedures will be controlled in accordance with TS Sections 6.5.3 and 6.8, which are subsections of the TS Administrative Controls Section ( 6.0). As a result, the deletion and subsequent relocation of this information from the TS complies with the guidance contained in GL 91-08. The proposed change, therefore, does not result in a technical change to the TS.
- c. Revise Bases Section 3/4.6.3, " Primary Containment Isolation Valves" (page B .
3/4 6-6) to include a clarification of those actions which constitute
" administrative controls" as used in TS 3.6.3, Footnotes (*) and (**), for locked or sealed closed containment valves which are permitted to be opened under "administmtive controls." This Bases Section is revised to add the following words:
" The opening of locked or sealed closed containment isolation valves on an intermittent basis under administrative control includes the following considerations: (1) stationing an operator, who is in constant communication with the control mom, at the valve controls, (2) instructing this operator to close these valves in an accident situation, and (3) assuring that environmental conditions will not preclude access to close the valves and that this action will prevent the release of radioactivity outside the containment."
Bases Section 3/4.6.3, " Primary Containment Isolation Valves" (page B 3/4 6-
- 6) is proposed to be revised to add the above wording. This change to the Bases Section is recommended by GL 91-08.
- 7. MOTOR-OPERATED VALVES TIIERMAL OVERLOAD PROTECTION
- a. Revise LCO 3.8.4.3 to delete reference to Table 3.8.4.3-1 and added the words, "...used in safety systems...", as denoted by the following:
"The thermal overload protection of each valve used in safety systems shall be OPERABLE."
LCO 3.8.4.3 is proposed to be revised to delete the reference to Table 3.8.4.3-1 (Motor-Operated Valves Thermal Overload Protection) and the LCO wording is revised accordingly. The table is being deleted from the TS
Attachment I to i NRC-94-0047 l Page 10 of 12 i
and relocated to the plant procedures. The list provided in Table 3.8.4.3-1 is not necessary to support the actions or surveillances required by the TS. The proposed word changes am consistent with the guidance provided in GL 91-08.
- b. Delete Table 3.8.4.3-1, " Motor-Operated Valves Thermal Overload Protection" and retain a single page with the following note: "3/4 8-21 through 3/4 8-24 are
'not used'," which will account for the skipped pages.
Table 3.8.4.3-1 is proposed to be deleted from the TS and relocated to plant procedures. The table currently denotes a list of requimd motor-operated valves with thennal overload protection including associated valve mimbers and systems affected. The list of required motor-operated valves with thermal overload protection is not necessary to support the actions or surveillances required by the TS. The information being relocated to plant procedures will be controlled in accordance with TS Sections 6.5.3 and 6.8, which are subsections of the TS Administrative Controls Section (6.0). As a result, the deletion and subsequent relocation of this infonnation from the TS complies with the guidance contained in GL 91-08. The proposed change, therefore, does not !
result in a technical change to the TS.
The proposed TS page changes are attached. They am written in accordance with the guidance in Reference 2.
EVALUATION This proposal relocates the component lists for Primary Containment Isolation Valves (TS Table 3.6.3-1) and Motor-Operated Valves Thermal Overload Protection (TS Table 3.8.4.3-1) to the plant procedures. Relocating these component lists to the plant procedures will allow Fermi 2 to administratively control changes to these tables in accordance with TS Sections 6.5.3 and 6.8. These administrative controls include requirements for the review of changes in accordance with 10CFR50.59. This specinc change, in itself, has no effect on the surveillance or system requirements and so, no effect on plant safety. Additionally, this proposed TS change is a line item TS improvement which is encouraged by Refemnce 2.
SJISNIFICANT IIAZARDS 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 i
- Attachment I to NRC-94-0047 Page 11 of 12 t
previously evaluated, or (2) create the possibility of a new or different kind of accident from any accident pmviously evaluated, or (3) involve a significant reduction in a margin of safety.
The proposed amendment will allow Fermi 2 to administratively control changes to the component lists for Primary Containment Isolation Valves and Motor-Operated Valves Thermal Overload Protection in accordance with the provisions of Generic Letter 91-08 (Reference 2) without the need to process a license amendment request. This modification is a line item TS improvement.
- 1. The proposed changes do not involve a significant increase in the pmbability or consequences of an accident previously evaluated. The proposed change will not result in any hardware or opemting changes. The proposed change is based upon Generic Letter 91-08 and merely remo';es component lists, removes details relating to the component lists, provides clarifying information supponing the mmoval of the-component listings, or removes details (which are considered administrative) that am no longer applicable to the TS. The removal of tabular component listings fmm the TS does not impact affected component OPERABILITY requirements. TS will continue to !
require the components to be OPERABLE. Action statements and surveillance ,
requirements for the components will also remain in the TS. The tabular component !
lists will be relocated to plant procedures which will be controlled in accordance with the provisions specified in the Administrative Controls Section of the TS. Therefore, this change is administrative in nature and does not involve a significant incmase in the probability or consequences of an accident previously evaluated. Further, the proposed changes do not alter the design, function, or operation of the components involved and therefore, do not affect the consequences of any previously evaluated accident.
- 2. The proposed changes do not create the possibility of a new or different kind of accident from any accident previously evaluated. The proposed changes will not impose any different operational or surveillance requimments. The changes propose to relocate these component lists to plant procedures whereby adequate contml of information is maintained. Further, as stated above, the proposed changes do not alter the design, function, or operation of the components involved and therefore, no new accident scenarios are created.
- 3. The proposed changes do not involve a signincant reduction in a margin of safety. The pmposed change will not reduce a margin of safety because it has no impact on any safety analysis assumption. The proposed change does not alter the scope of equipment currently required to be OPERABLE or subject to surveillance testing nor does the proposed change affect any instmment setpoints or equipment safety functions.
Therefore, the change does not involve a significant reduction in a margin of safety.
Attachment I to NRC-94-0047 Page 12 of 12 ENVIRONMENTAL IMPACT l
Detroit Edison has reviewed the proposed Technical SpeciGcation changes against the criteria of 10CFR51.22 for environmental considerations. The proposed changes do not involve a significant hazards consideration, nor signiGcantly change the types or significantly increase the amour.ts of effluents that may be released offsite, nor significantly increase individual or ctimulative occupational radiation exposures. Based on the foregoing, Detroit Edison .
concludes that the proposed Technical Specifications meet the criteria given in l 10CFR51.22(c)(9) for a categorical exclusion from the requirements for an Environmental i Impact Statement.
CONCLUSION Based on the evaluations 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 amendment will not be inimical to the common defense and security or the health and safety of the public.
In order to accomplish procedure changes associated with this change, Detroit Edison requests that the proposed license amendment be issued with a 60-day implementation period.
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