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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
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Y Douglas R Gapson T.r ..s r i <a<s+4
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Detroit -
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EC ISOn v July 29, 1993 NRC-93 -0061 U. S. Nucleac 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. ) "EWh Owners ' Group Licensing Topical Report -
Calibra tion Interval Extension," NEDC-32160P, December 1992
- 3) Detroit Edison letter to NRC, "D e t roit Edison Response to NRC Bulletin 90-01, Supplement 1,"
NRC-93 -0 03 7, datcd March 5, 1993
Subject:
Proposed Technical Specification Change (Licence Amendment) - Calibration Interval Extension Pursuant to ICCFR50.90 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. The proposed change extends instrument calibration intervals for celected instrumentation to 36 months.
The proposed Technical Specification changes are supported by an analysis performed by the EWR Csmers' Group (Reference 2), which demonstrates that other periodic tests required by Technical Specifications, such as channel checks, channel functional tests, logic system functional tests, are adequate to assure performance within acceptance limits. The applicability of the reference analysis techniques to Fermi 2 has been verified. In addition, General Electric has per formed an analysis of other instruments used at Fermi 2 using the Reference 2 techniques.
Detroit Edison's evaluation of the proposed change as well as the accompanying signifiermt hazards consideration analysis is provided as Enclosure 1. The General Electric plant-specific report is provided as Enclosure 2. The proposed Technical Specification page changes are provided as Enclosure 3.
This proposal will reduce equipment wear f rom unnecessary t est cycles, reduce out-of-service time due to calibration and reduce Engineered fp 030007 p g i ')
9aOeOaO m 920 m PDR ADDCK 05000241 n Mq P ppR , f
i USNRC July 29, 1993 NRC-93-0061 ;
Page 2 !
J Safety Feature actuations. In addition, the change involves a ,
significant cost savings ~ by eliminating a significant amount of instrument calibration work from each refueling outage scope. This elimination will save at least 2.2 million dollars - (in current '
dollars) over the remainder of the current operating license. ~
I' Detroit Edison has evaluated the proposed Technical Specifications against the criteria of 10CFR50.92 and determined that no significant j hazards consideration is involved. ' The Fenmi 2 Onsite Review .
Organization has approved and the Nuclear Safety Review Group has reviewed the proposed Technical Specifications and concurs with the t enclosed determinations. In accordance with 10CFRSO.91, Detroit ,
Edison has provided a copy of this letter to the State of Michigan.- ,
The information in Enclosure 2 to this letter has been identified by General Electric (GE) as proprietary information. Included in Enclosure 2 is GE's affidavit to that effect. Therefore,' in accordance with 10CFR2.790, it is requested that Enclosure 2 be .I withheld from public disclosure. !
t If you have any questions, please contact Mr. Glen D. Ohlemacher at j (313) 586-4275.
Sincerely, f t
Enclosure [
cc: T. G. Colburn !
W. J. Kropp !
J . B. Ma rtin i M. P. Phillips f Supe rvis or, Electric Operators, Michigan Public Service Commission - J. R. Padgett h
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USNRC 4
July ~29, 1993 NRC-93-0061 Page 3 i
l I, DOUGLAS R. GIPSON, do hereby af firm that the foregoing statements are based on f acts and circumstances which are true and accurate to ,
the best of my_ knowledge and belief.
y + Y DOUGLAS R. GIPSON Senior Vice President On this day of __ t /hdr . 1993, before me .
hon, personally appeared that he executed the Douglas foregoingR.asj Gip /his free act and deed.peir g first duly sworn and say i
h 14Lw 4/ W C' Notary Public NOTARYMONROE PUBUCSTm OF MODCm UyJNry i 1
N NWalON EXP. NOV. M1095 h l
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-- d, Enclosure 1 t,o NRC-93-0061 Page 1 i
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ENCLOSURE 1 EVALUATION OF PROPOSED CHANGE AND NO SIGNIFICANT HAZARDS EVALUATION 1
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Enclosure 1 to NRC-93-0061 Page 2 INTRODUCTION This proposed change is to extend instrument calibration intervals to 36 months for selected instrumentation. Industry experience has demonstrated that other periodic tests required by Technical Specifications, such as channel checks, channel functional tests, and logic system functional tests provide adequate assurance that instrument performance is within acceptance limits.
EVALUATION An analysis technique has been developed by General Electric for the BWR Owners' Group which provides the basis for justifying instrument drift allowances based on as-found, as-left data (Reference 2). The analysis was performed for representative BWR instrumentation, and the results are applicable to Fermi 2. In addition, General Electric has performed a plant specific evaluation to extend the Reference 2 evaluation to additional instrumentation (Enclosure 2). The Enclosure 2 evaluation is intended to be used in conjunction with the Reference 2 report.
Plant operating experiences were reviewed to identify instrument failures and how they were detected. The failures were identified or would have been identified by other testing requirements contained in Technical Specifications (channel check, channel functional test, and logic system functional test) and by operators. The exception to this statement is the Rosemount pressure transmitter slow loss of fill-oil phenomenon discussed below.
These other tests are normally sufficient to identify failure modes or degradations in instrument performance and assure operation of the analyzed instrument loops within acceptance limits.
The evaluations of Reference 2 and Enclosure 2 demonstrate that the calibration interval can be extended to 36 months for the instrumentation listed in Table 1.
In each case, the functional unit involved is monitored by regular channel checks required by the Technical Specifications. Also, the instrumentation involved has either been evaluated in Reference 2 or the Enclosure 2 extension of Reference 2. The appropriate document is
, indicated in Table 1.
For this instrumentation, the instrument drift determined in Reference 2 or Enclosure 2 was used in conjunction with the NRC approved General Electric Instrument Setpoint Methodology (NEDC-31336). These
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NRC-93-0061 :
Page 3 i
i evaluations were performed using a calibration frequency of 45 months, corresponding to the proposed 36 month frequency plus the 25% overrun '
allowed by Specification 4.0.2. The evaluations determined that no change to the Trip Setpoints or Allowable Values specified in the Technical Specifications is needed to accommodate the extended l calibration frequency. l A concern related to calibration extension is the phenomenon of slow loss of fill-oil in Rosemount pressure transmitters. Detroit Edison ;
has committed to remove all remaining Rosemount pressure transmitters j of concern by the completion of Fermi 2's fourth refueling in the l spring of 1994 (Reference 3). Thus, the slow fill-oil loss concern j
does not impact the proposed change since the earliest implementation ;
for this change is also the fourth refueling. l l
The calibration extension is proposed to be implemented in a staggered fashion. Each functional unit proposed for extension consists of at least two channels. The proposed TS will require at least one-half of the channels for each functional unit to be tested at least every 18 months. This requirement is applied by a ** footnote to Technical
]
Specification Table 1.1 where appropriate, or by wording in the l Surveillance Requirement itself. I This staggering will assure that at least one channel for each functional unit is calibrated at least once every 18 months. This will provide a means to detect generic problems within a functional ;
unit without waiting a possible 36 months or more between ;
calibrations. '
The TS included in the Reference 2 Topical Report includes a change to the Specification 1.19 definition of Logic System Functional Test j (LSFT). The change allows the sensor to be excluded from the LSFT.
1 The sensor functionality is tested during the channel calibration. ,
LSFT's are performed typically at an 18-month interval. In order to i obtain the benefits of the calibration interval extension the sensor j must be excluded from the LSFT definition. This is acceptable since l the reliability of sensor performance is monitored by periodic channel check surveillances.
SIGNIFICANT I!AZARDS CONSIDERATION In accordance with 10CFR50.92, Detroit Edison has made a determination that the proposed amendment involves no significant hazards considerations. To make this determination, Detroit Edison must establish that operation in accordance with the proposed amendment i
. to NRC-93-co61 Page 4 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 previously evaluated, or 3) involve a significant reduction in a margin of safety.
The proposed change to extend to 36 months the calibration interval of selected instrumentation does not:
- 1) Involve a significant increase in the probability or consequences of an accident previously evaluated. The purpose of the proposed Technical Specification change is to extend calibration interval testing requirements for selected instrumentation. Ilowever, s because of the continued application of redundant Technical Specification requirements such as channel checks, channel l functional tests, and logic system functional tests, the '
performance of these instruments will be maintained within the l
acceptance limits assumed in plant safety analyses and required for successful mitigation of an initiating event. The proposed Technical Specification changes do not affect the capability of the associated systems to perform their intended function within their instrument settings.
These other tests are sufficient to identify failure modes or degradations in instrument performance and ensure operation of the associated systems within acceptance limits. There are no credible failure modes that can be detected by instrument calibration that cannot also be detected by other Technical Specification tests.
- 2) Create the possibility of a new or different kind of accident from any accident previously evaluated. As discussed above, the '
proposed Technical Specification changes do not affect the ;
capability of the associated systems to perform their intended l function within the acceptance limits assumed in plant safety analyses and required for successful mitigation of an initiating event. All plant systems continue to operate in an identical !
manner. No new accident modes are created.
- 3) Involve a significant reduction in a margin of safety. The current Technical Specification allowable values are based on the maximum analytical limits assumed in the plant safety analyses.
These analyses conservatively establish the margin of safety.
The proposed Technical Specification changes do not affect the capability of the associated systems to perform their intended function within the instrument settings used as the basis for the plant safety analyses. Plant and system settings to an
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Page 5 initiating events will remain in compliance within the assumptions of the safety analyses, and therefore the margin of safety is not affected.
Although not explicitly evaluated, the proposed Technical Specification changes may increase the margin of safety by:
o Heducing the amount of time that systems are out-of-service for the performance of instrument calibration.
o Reducing actuations of Engineered Safety Features, o Reducing wear-and-tear on equipment resulting from unnecessary test cycles.
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 radiation exposures. Based on the foregoing, Detroit Edison concludes that the proposed Technical Specifications do meet the criteria given in 10CFR51.22(c)(9) for a categorical exclusion from the 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.
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Enclosure 1 to Table 1 NRC - 93 0061 Instrumeriiation For Extension of Calibration interval to 36 Months Pace 6 - 11 Signal Indicator /
Conditioner: Recorder: !
Sensor Sensor Trip Unit Trip Unit (Manufacturer / (Manufacturer / Analysis Tech Spec Description Manufacturer Model No Manufacturer Model No Model No) Modei No) ' Report 4.3.1.1-1 Reactor Protection System Instrumentation ,
BWROG Reactor Vessel Steam Dome Pressure-High 510/71000 NA NA **
4.3.1.1 -1.3 Rosemount 1153 Rosemount j 4.3.1.1-1.4 Reactor Vessel Low Water Level-Level 3 Rosemount 1153 Rosemount 510DU NA NA BWROG 4.3.1.1-1.7 Drywell Pressure-High Rosemount 1153 Rosemount 5100U NA NA BWROG 4.3.2.1-1 Isolation Actuation instrumentation 4.3.2.1 1.1 Primary Containment isolation l t
4.3.2.1-1.1.a.1 Reactor Vessel Low Water Level-Level 3 Rosemount 1153 Rosemount 510DU NA NA BWROG !
4.3.2.1-1.1.a.2 Reactor Vessel Low Water Level-Level 2 Rosemount 1153 Rosemount 510DU NA NA BWROG ;
4.3.2.1 -1,1.a.3 Reactor Vessel low Water Level. Level 1 Rosemount 1153 Rosemount 510/710DU NA NA BWROG 4.3.2.1-1.1.b Drywell Pressure-High Rosemount 1153 Rosemount 510DU NA NA BWROG ,
5 4. m ' l 1.c.2 Main Steam Line Pressure-Low Rosemount 1151 Rosemount 510/710DU NA NA BWROG 510/
4.3. 2.1 - 1.1.c. 3 Main Steam Line Flow-High Rosemount 1151 Rosemount 710DU NA NA BWROG 122-4.3.2.1-1.1.d Main Steam Line Tunnel Temperature- High PYCO '
1021-04 Rosemount 510DU NA NA BWROG .!
4.3.2.1-1.1.e Condenser Pressure - High Rosemount 1151 Rosemount 510DU NA NA BWROG 122-
+
4.3.2.1 - 1.1. f : Turbine Bldg Area Tempera +ure- High PYCO 1021 44 Rosemount 510DU NA NA BWROG 4.3.2.1-1.2 Reactor Water Cleanup System isolation .
Heat Exchanger / Pump / High Energy Piping Area 4.3.2.1-1.2.b Temperature-High PYCO
- 102-9093 Riley 86A NA NA BWROG Heat Exchanger / Pump / Phase Separator Area l 4.3 2.1 -1.2.c Ventilation Dif ferential Temperature -High PYCO
- 102-9093 Riley 86A NA NA BWROG 1 l 4.3.2.1-1.2.e Reactor Vessel low Water Level-Level 2 Rosemount 1153 Rosemount 510Dt) NA NA BWROG' i '
i ' Operability verification is performed as per Channel Calibration definition (1.4) of Fermi 2 Tech Spec.
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Enclosure 1 to Table 1 NRC 0061 instrumentation For Extension of Calibration interval to 36 Months Page 7 - 11 Signal Indicator /
Conditioner: Recorder:
Sensor Sensor Trip Unit Trip Unit (Manufacturer / (Manufacturer / Analysis Tech Spec Description Manufacturer Model No Manufacturer Model No Model No) Model Nc) Report 4.3.2.1-1.3 Reactor Core Isolation Cooling System isolation l
4.3.2.1-1.3.a.1 RCIC Steam Line Flow riigh, Differential Pressure Rosemount 1151 Rosemount 510DU NA NA B'NROG 4.3.2.1-1.3.b RCIC Steam Supply Pressure-Low Rosemount 1151 Rosemount 510DU NA NA BWROG 4.3.2.1-1.3.c RCIC Turbine Exharst Diaphragm Pressure-High Rosemount . 1151 Rosemount 510/7100U NA NA BWROG N145C 4.3.2.1 1.3.d RCIC Equipment Room Temperature-High GE
- 3224P1 Riley 86A NA NA BWROG
- 4.3.2.1-1.4 High Pressure Coolant injection System isolation 4.3.2.1-1.4.a.1 HPCI Steam Line Flow-High, Differentiat Pressure Rosemount 1153 Rosemount 710DU NA NA BWROG 4.3.2.1-1.4.b HPCl Steam Supply Pressure-Low Rosemount 1153 Rosemount 510/710DU NA fsA BWROG 4.3.2.1-1.4.c HPCI Turbine Exhaust Diaphragm Pressure-High Rosemount 1153 Rosemount 510/710DU NA NA BWROG N145C 4.3.2.1-1.4.d HPCI Equipment Room Temt pture-High GE 3224P1 Riley 86A NA lNA BWROG
.3.2. 1 -1.5 RHR System Shutdown Cooling Mode Isolation 4.3.2.1 -1. 5.a Reactor Vessel Low Water level-Level 3 Rosemount 1153 Rosemount 510DU NA NA BWROG Reactor Vessel (Shutdown Cooling Cut-in Permissive 4.3.2.1-1.5.b Interlock) Pressure-High Rosemount 1153 Rosemount 510/710DU NA NA BWROG 4.3.2.1-1.6 Secondary Containment Isolation 4.3. 2.1 -1. 6.a Reactor Vessel low Water level-level 2 Rosemount 1153 Rosemount 5100U NA NA BWROG 4.3.2.1 -1.6.b Drywell Pressure-High Rosemount 1153 Rosemount 510DU NA NA BWROG
- Operability verification is performed as per Channel Calibration definition (1.4) of Fermi 2 Tech Spec.
4 Y
-.- _. :--.4. - - . - . = - - - . .e--...- -- - - - - -,--- . - - - - . ., ,,. .m ..-,-2 r - .--.,,.--.,-..-m ,--.,,..r.,.--..e.-- -_ e-+-..-..v-+.--rw--,--.-r-- . . ~ , - . - . ..-...-w. ---.,--o.m--'
Enclosure 1 to Table 1 NRC 0061 Instrumentation For Extension of Calibration Interval to 36 Months Page 8 - 11 Signal indicator /
Conditioner: Recorder:
Sensor Sensor Trip Unit Trip Unit (Manufacturer / (Manufacturer / Analysis Tech Spec Description Manufacturer Model No Manufacturer Model No Model No) Model No) Report Emergency Core Cooling System Actuation instrumentation '
4.3.3.1-1 4.3.3.1 -1.1 Core Spray System 4.3.3.1-1,1.a Reactor Vessel low Water Level-level 1 Rosemount 1153 GE 184C5988 NA NA BWROG 4.3.3.1-1.1.b Drywell Pressure-High Rosemount 1153 Rosemount 510DU NA NA BWROG 4.3.3.1-1.1.c Reactor Steam Dome Pressure-Low Rosemount 1153 Rosemount 510/710DU NA NA RWhOd 4.3.3.1-1.2 Low Pressure Coolant injection Mode of the RHR System 4.3.3.1-1.2.a Reactor Vessel Low Water Level-Level 1 Rosemount 1153 GE 184C5988 NA NA BWROG 4.3.3.1-1.2.b Drywell Pressure-High Rosemount 1153 Rosemount 510DU NA NA BWROG 4.3.3.1-1.2.c Reactor Steam Dome Pressure-Low Rosemount 1153 Rosemount 510/710DU NA NA BWROG 4.3.3.1-1.2.d Reactor Vessel Low Water Level-level 2 Rosemount 1153 GE 184C5988 NA NA BWROG 4.3.3.1 -1.2.e Reactor Steam Dome Pressure-Low Rosemount 1153 Rosemount 510/710DU NA NA BWROG 4.3.3.1-1.2.f Riser Differential Pressure-High Rosemount 1153 Rosemount 510/710DU NA NA BWROG 4.3.3.1-1.2.g Recirculation Pump Differential Pressure-High Rosemount 1153 Rosemount 510/710DU NA NA BWROG 4.3.3.1 -1.3 High Pressure Coolant injection System 4.3.3.1 -1.3.a Reactor Vessel Low Water Level-Level 2 Rosemount 1153 GE 184C5988 NA NA BWROG 4.3.3.1-1.3.b Drywell Pressure-High Rosemount 1153 Rosemount 510DU NA NA BWROG 1151/
4.3.3.1-1.3.c Condensate Storage Tank Level-Low Rosemount 1152 Rosemount 5100U NA NA BWROG 4
4.3.3.1-1.3,e Reactor Vessel High Water Level-level 8 Rosemount 1153 GE 184C5988 NA NA BWROG e
r*~ase- w e5 - =----w m e we- o-+m--m-v r ere-.-m+- e,we--- +>-wwee we- m %-e-- s e-eme- ew .ct rww --3ei r- -+-- e e m an- * + we e v e e .w rwe-e - -
- w w er --e -s *=,c . ,,. .rw,. ,-.4 ...cw.n ~-,.w,c.,a ,,...-,-..,..w. r-,,qw-=.,,,,. ..m.w.,em'
Enclosure 1 to Table 1 NRC 0061 instrumentation For Extension of Calibration Interval to 36 Months Page 9 - 11 Signal Indicator /
Conditioner: Recorder:
Sensor Sensor Trip Unit Trip Unit (Manufacturer / (Manufacturer / Analysis Tech Spac Description Manufacturer Model No Manufacturer Model No Model No) Model No) Report 4.3.3.1 1.4 Automatic Depressurization System l
4.3.3.1-1.4.a Reactor Vessel Low Water Level-Level 1 Nsemount 1153 GE 184C5988 NA NA BWROG 4.3.3.1-1.4.b Dryweil Pressure-High Rosemount 1153 Rosemount 510/710DU NA NA BWROG l 4.3.3.1-1.4.d Core Spray Pump Discharge Pressure-High Rosemount 1153 Rosemount 510/710DU NA NA BWROG 4.3.3.1-1.4.e RHR LPCI Mode Pump Discharge Pressure-High Rosemount 1153 Rosemount 510/710D0 NA NA BWROG 4.3.3.1 - 1.4.f Reactor Vessel Low Water level-level 3 Rosemount 1153 Rosemount 510/710DU NA NA BWBOG 4.3.4-1 ATWS Recirculation Pump Trip Actuation Instrumentation 4.3.4 1.1 Reactor Vessel Low Water level-Level 2 Rosemount 1153 GE 184C5988 NA NA BWROG 4.3.4-1.2 Reactor Vessel Pressure-High Rosemount 1153 GE 184C5988 NA NA BWROG 4.3. 5.1 -1 Reactor Core Isolation Cooling System Actuation Instrumentation 4.3.5.1 1.a Reactor Vessel Low Water Level-level 2 Rosemount 1153 GE 184C5988 NA NA BWROG 4.3.5.1-1.b Reactor Vessel High Water Level-Level 8 Rosemount 1153 GE 184C5988 NA NA BWROG 1151/
, 4.3.5.1-1.c Condensate Storage Tank Level-Low Rosemount 1152 Rosemount 510DU NA NA BWROG 4.3.7.4-1 Remote Shutdown Monitoring Instrumentation Analogic / Pl j 4.3. 7.4 - 1.1 Reactor Vessel Pressure Rosemount 1152 NA NA NA 2455 BWROG 4.3.7.4-1.2 Reactor Vessel Water Level Rosemount 1153 GE 184C5988 TEC/156M Weston/1316 BWROG Transmation/
! 4.3.7.4-1.3 Suppression Chamber Water Temperature Conax
- 7N62 NA NA 610T Weston/1316 BWROG Analogic / Pi .
4.3.7.4-1.4 Drywell Pressure Rosemount 1153 NA NA NA 2455 BWROG I Hays Republic /
4.3.7.4-1.5 RHR Division i Hx Discharge Flow Rosemount 1153 NA NA GEMAC/ 565 3600 BWROG
- Operability verification is performed as per Channel Calibration definition (1.4) of Fermi 2 Tech Spec.
Enclosure 1 to Table 1 NRC - 93 0061 Instrumentation For Extension of Calibration Interval to 36 Months Page 10 - 11 Signal Indicator / -
I Conditioner: Recorder:
Sensor Sensor Trip Unit Trip Unit (Manufacturer / (Manufacturer / Analysis Tech Spec Description Manufacturer Model No Manufacturer Model No Model No) Model No) Report .
4.3.7.5-1 Accident Monitoring Instrumentation L&N/Speedo 4.3.7.5-1.1 Reactor Vessel Pressure Rosemount 1152 NA NA NA Max M BWROG Weston/1316 &
L&N/
4.3.7.5-1.2.a Reactor Vessel Water Level-Fuel Zone Rosemount 1153 Rosemount 510DU NA SpeedoMax M BWROG L&N/ Speedo 4.3.7.5-1.2.b Reactor Vessel Water Level Wide Range Rosemount 1153 GE 184C5988 NA Max M BWROG L&N/ Speedo ,
4.3.7.5-1.3 Suppression Chamber Water Level Rosemount 1153 NA NA NA Max M BWROG Westronics/
4.3.7.5-1.4 Suppression Chamber Water Temperature Conax
- 7080 NA NA NA 3000C BWROG Westronics/ !
4.3.7.5-1.5 Suppression Chamber Air Temperature Conax '
7880 NA NA NA 3000C BWROG Westronics/
4.3.7.5-1.6 Suppression Chamber Pressure Rosemount 1153 NA NA NA 2100C BWHOG Westronics/
4.3.7.5-1.7 Drywell Pressure, Wide Range Rosemount 1153 NA NA NA 2100C BWROG Westronics/
4.3.7.5-1,8 Drywell Air Temperature Conax
- 7B80 NA NA NA 3000C BWROG 4.3.9.1-1 Feedwater/ Main Turbine Trip Actuation Instrumentation 4.3.9.1-1.3 Reactor Vessel High Water Level-Level 3 Rosemour.t 1153 Rosemount 510/710DU NA NA BWROG 4.3.11.1-1 Appendix R Alternative Shutdown Instrumentation 4.3.11.1-1.5 Condensate Storage Tank Level Rosemount 1151 NA NA NA Chessell/ 700 BWROG 4.3.11.1-1.7 Reactor Water Level Rosemount 1153 NA NA NA Chessell/ 700 BWROG Transmation/ Foxboro/
, 4.3.11.1-1.8 Reactor Pressure Rosemount 1153 NA NA 230T 6402HC BWROG Thermoelectric Transmation/
4.3.11.1-1.9 Torus Water Temperature
- 1T3210A NA NA 610T Chessell/ 700 BWROG 4.3.11.1-1.10 Torus Water Level Rosemount 1151 NA NA NA Chessell/ 700 BWROG Thermoelectric Transmation/
4.3.11.1-1.11 Primary Containment Temperature
- AD14TUR NA NA G10T Chessell/ 700 BWROG
- Operability verification is performed as per Channel Calibration definition (1.4) of Fermi 2 Tech Spec.
4
, _y,~_-,-, ,#.--., %-g,-.n._,,- ,,..,-,2 e m r e- mw~ -~
m-- = = w---- .- w-.-- ww w~ w --*wwwe--v---. +r---==---e- =v--wmv-ne-e'v--~*-ewe--- s ---e.w=m *v- 1 +-m=h--%-- - - - - - -* - * -e--wi -ew& -wwau ce - w w nT
Enclosure 1 to Table 1 - '
NRC - 934061 Instrumentation For Extension of Calibration Interval to 36 Months Page 11 - 11 Signal Indicator /
Conditioner: Recorder:
Sensor Sensor Trip Unit Trip Unit (Manufacturer / (Manufacturer / Analysis ,
Tech Spec Description Manufacturer Model No Manufacturer Model No Model No) Model No) Report '
4.4.2.2 Safety / Relief Valves Low-Low Set Function 4.4.2.2.b CHANNEL CAllBRATION at least once per 36 months Rosemount 1153 GE 184C5988 NA NA BWROG 4.6.1.4 Primary Containment / MSIV Leakage Control System Foxboro/ 6402
!- N2AO-L2C- Foxboro/ N2Al- & Hays Republic / BWROG/
4.6.1.4.d.3 CHANNEL CAllBR ATION at least once per 36 months Rosemount 1153 Foxboro R 13V 3600 GE 4.6.2 Depressurization Systems / Suppression Chamber Verify eight suppression pool water temperature instrumentation channels OPERABLE by performance of a CHANNEL CAllBRATION at least once per 36 Westronics/ j 4.6.2.1.f.3 months,. Conax
- 7B80 NA NA NA 2400 BWROG Verify both narrow range suppression chamber water levelinstrumentation channels OPERABLE by performance of a CHANNEL CALIBRATION at least N2AP+ Foxboro/ N2Al- BWROG /
4.6.2.1.g.3 once per 36 months. Rosemount 1153 Foxboro ALM-AR 13V Weston/1316 GE
- Operability verification is performed as per Channel Calibration definition (1.4) of Fermi 2 Tech Spec.
- GE - General Electric Plant Specific Report, Enclosure 2.
4D
_ _ _ _ _ _ . _ - _ __.,_._m __ _ _.., _ __. . . _ - ,._,._c.___- - _ ..m.,m__ . . , . .,+.% E_m..,...m.;-w%_m_,_ - _ . .
y%. ._%. , ...m.,_.... . ,w,< , ,,,_,<.;,,,.,,,...~+_.,,_. ~, . , - . , , -