Similar Documents at Fermi |
---|
Category:OPERATING LICENSES-APPLIATION TO AMEND-RENEW EXISTING
MONTHYEARNRC-99-0082, Application for Amend to License NPF-43,revising TS 3/4.6.1.8 to Allow Continued Operation Until Next Plant Shutdown at Which Time Valve T4803F601 Will Be Repaired1999-09-24024 September 1999 Application for Amend to License NPF-43,revising TS 3/4.6.1.8 to Allow Continued Operation Until Next Plant Shutdown at Which Time Valve T4803F601 Will Be Repaired NRC-99-0072, Application for Amend to License NPF-43,revising SRs & Bases for Div I Battery Sys to Agree with Design of New Battery Replacement1999-09-10010 September 1999 Application for Amend to License NPF-43,revising SRs & Bases for Div I Battery Sys to Agree with Design of New Battery Replacement NRC-99-0078, Rev 14 to Application for Amend to License NPF-43,providing Update for Remaining Open Issues Associated with NRC Review of ITS Submittal.Brief Abstract of Changes Included in Rev & Revised Pages for Submittal & Rev Instructions,Included1999-08-25025 August 1999 Rev 14 to Application for Amend to License NPF-43,providing Update for Remaining Open Issues Associated with NRC Review of ITS Submittal.Brief Abstract of Changes Included in Rev & Revised Pages for Submittal & Rev Instructions,Included NRC-99-0048, Application for Amend to License NPF-43 to Change TS to Include Provisions for Enabling Oscillation Power Range Monitor (OPRM) Upscale Function in Average Power Range Monitor (Aprm).Draft TS Pages Encl1999-07-30030 July 1999 Application for Amend to License NPF-43 to Change TS to Include Provisions for Enabling Oscillation Power Range Monitor (OPRM) Upscale Function in Average Power Range Monitor (Aprm).Draft TS Pages Encl NRC-99-0035, Application for Amend to License DPR-9 to Modify TS Section D.3.Amend Would Eliminate TS Surveillance Requirement for Ni Cover Gas on Nearly Empty Primary Sodium Storage Tanks in Sodium Bldg Complex.With marked-up & Typed TS Pages1999-04-20020 April 1999 Application for Amend to License DPR-9 to Modify TS Section D.3.Amend Would Eliminate TS Surveillance Requirement for Ni Cover Gas on Nearly Empty Primary Sodium Storage Tanks in Sodium Bldg Complex.With marked-up & Typed TS Pages NRC-99-0025, Application for Amend to License NPF-43,modifying TS SR 4.4.1.1.1 to Require Each Recirculation Pump Discharge Valve Be Demonstrated Operable at Least Once Every 18 Months & Deleting Footnote That Applies to TS 4.4.1.1.11999-03-23023 March 1999 Application for Amend to License NPF-43,modifying TS SR 4.4.1.1.1 to Require Each Recirculation Pump Discharge Valve Be Demonstrated Operable at Least Once Every 18 Months & Deleting Footnote That Applies to TS 4.4.1.1.1 NRC-98-0122, Rev 1 to 980403 Application for Amend to License NPF-43, Proposing TS Change for Conversion to Improved Standard Ts. Revised Pages for Submittal & Brief Abstract of Changes, Encl1998-09-28028 September 1998 Rev 1 to 980403 Application for Amend to License NPF-43, Proposing TS Change for Conversion to Improved Standard Ts. Revised Pages for Submittal & Brief Abstract of Changes, Encl NRC-98-0128, Rev to 980128 Application for Amend to License DPR-9, Revising TS to Implement Provisions of 1996 Decommissioning Rule,Including Requirements for Control of Effluents,Dose Limits & Annual Reporting of 10CFR50.36a1998-08-26026 August 1998 Rev to 980128 Application for Amend to License DPR-9, Revising TS to Implement Provisions of 1996 Decommissioning Rule,Including Requirements for Control of Effluents,Dose Limits & Annual Reporting of 10CFR50.36a NRC-98-0117, Application for Amend to License NPF-43,revising Table 4.0.2-1 to Include Two Functional Units for TS 4.3.1.3 (RPS Response Time Testing) & Allowing one-time Extension of Respective Surveillance Intervals1998-07-23023 July 1998 Application for Amend to License NPF-43,revising Table 4.0.2-1 to Include Two Functional Units for TS 4.3.1.3 (RPS Response Time Testing) & Allowing one-time Extension of Respective Surveillance Intervals NRC-98-0044, Application for Amend to License DPR-9,allowing Util to Possess Special Nuclear Matl in Quantity Totaling No More than 15 Grams of U-235,U-233 or Pu,Or Any Combination Thereof,W/Pu Activity Totaling No More than 2 Ci1998-07-17017 July 1998 Application for Amend to License DPR-9,allowing Util to Possess Special Nuclear Matl in Quantity Totaling No More than 15 Grams of U-235,U-233 or Pu,Or Any Combination Thereof,W/Pu Activity Totaling No More than 2 Ci NRC-98-0040, Application for Amend to License NPF-43,requesting to Allow one-time Extension of Surveillance Intervals to Delay Shutdown for Upcoming Sixth Refueling Outage (RFO6) Until 9809041998-06-26026 June 1998 Application for Amend to License NPF-43,requesting to Allow one-time Extension of Surveillance Intervals to Delay Shutdown for Upcoming Sixth Refueling Outage (RFO6) Until 980904 ML20248L7981998-06-0505 June 1998 Application for Amend to License NPF-43,revising TS Section 2.1.2.Proprietary & non-proprietary Info,Encl.Proprietary Info Withheld NRC-98-0065, Application for Amend to License NPF-43,to Add Configuration Risk Mgt Program to TS Section 6.8.5,contingent on Approval of Previously Submitted License Amend for TS 3.8.1.11998-04-27027 April 1998 Application for Amend to License NPF-43,to Add Configuration Risk Mgt Program to TS Section 6.8.5,contingent on Approval of Previously Submitted License Amend for TS 3.8.1.1 NRC-98-0071, Application for Amend to License NPF-43,proposing Align Shutdown Action Statements for Primary Containment Oxygen Monitoring Instrumentation in Three Specifications1998-04-0909 April 1998 Application for Amend to License NPF-43,proposing Align Shutdown Action Statements for Primary Containment Oxygen Monitoring Instrumentation in Three Specifications NRC-98-0043, Application for Amend to License NPF-43 to Convert Current TS to Improved Ts.Meeting Is Requested to Discuss Review Schedule & Contents of Amend.Vol 1 Includes Application & Justification.Vols 2-13 Contain Improved TS1998-04-0303 April 1998 Application for Amend to License NPF-43 to Convert Current TS to Improved Ts.Meeting Is Requested to Discuss Review Schedule & Contents of Amend.Vol 1 Includes Application & Justification.Vols 2-13 Contain Improved TS NRC-98-0062, Application for Amend to License NPF-43,modifying Drywell Oxygen Monitoring Instrumentation Action Requirements to Be Consistent W/Those Contained in NUREG-1433,Rev 1, STS GE Plants,BWR/41998-04-0202 April 1998 Application for Amend to License NPF-43,modifying Drywell Oxygen Monitoring Instrumentation Action Requirements to Be Consistent W/Those Contained in NUREG-1433,Rev 1, STS GE Plants,BWR/4 NRC-98-0057, Application for Amend to License NPF-43,revising Requirements Associated W/Containment Oxygen & Hydrogen Monitors1998-04-0202 April 1998 Application for Amend to License NPF-43,revising Requirements Associated W/Containment Oxygen & Hydrogen Monitors NRC-98-0033, Application for Amend to License NPF-43,eliminating Incorrect Descriptive Info Re Water Inventory in CST Reserved for Hpci/Rcic & Raising CST Min Water Level for Core Spray1998-03-27027 March 1998 Application for Amend to License NPF-43,eliminating Incorrect Descriptive Info Re Water Inventory in CST Reserved for Hpci/Rcic & Raising CST Min Water Level for Core Spray NRC-98-0034, Application for Amend to License NPF-43,revising Footnote Specifying Conditions Where Isolation Valves Associated W/ LPCI Sys Operation Are Repositioned1998-03-27027 March 1998 Application for Amend to License NPF-43,revising Footnote Specifying Conditions Where Isolation Valves Associated W/ LPCI Sys Operation Are Repositioned NRC-98-0003, Application for Amend to License NPF-43,revising Tech Specs to Improve Administrative Controls Re thermal-hydraulic Stability & Idle Recirculation Loop Startup & Eliminating Neutron Flux Indication from TS1998-01-28028 January 1998 Application for Amend to License NPF-43,revising Tech Specs to Improve Administrative Controls Re thermal-hydraulic Stability & Idle Recirculation Loop Startup & Eliminating Neutron Flux Indication from TS NRC-98-0027, Application for Amend to License DPR-6,modifying Sections F & I of Plant TS to Include Requirements for Control of Effluents,Dose Limits & Annual Reporting Per 10CFR50.36a1998-01-28028 January 1998 Application for Amend to License DPR-6,modifying Sections F & I of Plant TS to Include Requirements for Control of Effluents,Dose Limits & Annual Reporting Per 10CFR50.36a NRC-98-0006, Application for Amend to License NPF-43,changing Surveillance Interval in TS 4.4.3.2.2.a by Extending It from Current 18 Month Testing Interval to 24 Month Testing Interval to Be Consistent W/Asme Code Requirements1998-01-28028 January 1998 Application for Amend to License NPF-43,changing Surveillance Interval in TS 4.4.3.2.2.a by Extending It from Current 18 Month Testing Interval to 24 Month Testing Interval to Be Consistent W/Asme Code Requirements NRC-98-0002, Application for Amend to License NPF-43,revising SRs for Div II Battery Sys to Agree W/Design of New Battery Replacement1998-01-28028 January 1998 Application for Amend to License NPF-43,revising SRs for Div II Battery Sys to Agree W/Design of New Battery Replacement NRC-98-0008, Application for Amend to License NPF-43,revising Footnotes Specifying Conditions Under Which SRs Associated W/Ts 3/4.9.1, Reactor Mode Switch, Can Be Performed1998-01-28028 January 1998 Application for Amend to License NPF-43,revising Footnotes Specifying Conditions Under Which SRs Associated W/Ts 3/4.9.1, Reactor Mode Switch, Can Be Performed NRC-98-0023, Application for Amend to License DPR-9,allowing Util to Possess Contaminated Apparatus & Equipment & Radioactive Sources at Fermi 1 Containing Byproduct Matl Not Produced by Operation of Plant Reactor1998-01-28028 January 1998 Application for Amend to License DPR-9,allowing Util to Possess Contaminated Apparatus & Equipment & Radioactive Sources at Fermi 1 Containing Byproduct Matl Not Produced by Operation of Plant Reactor NRC-98-0025, Application for Amend to License DPR-9,changing TS on Access Control to Provide Flexibility While Maintaining Similar Controls Over Access1998-01-28028 January 1998 Application for Amend to License DPR-9,changing TS on Access Control to Provide Flexibility While Maintaining Similar Controls Over Access NRC-97-0115, Application for Amend to License DPR-9,modifying Part 2.A in Order to Delete Reference to Six Letters Now Listed & Instead Refer to Encl Fermi 1 SAR1997-12-15015 December 1997 Application for Amend to License DPR-9,modifying Part 2.A in Order to Delete Reference to Six Letters Now Listed & Instead Refer to Encl Fermi 1 SAR NRC-97-0105, Application for Amend to License NPF-43,revising TS to Be Consistent W/Planned Replacement of Current Power Range Monitoring Portion of Existing Nms1997-12-10010 December 1997 Application for Amend to License NPF-43,revising TS to Be Consistent W/Planned Replacement of Current Power Range Monitoring Portion of Existing Nms ML20211J1971997-09-29029 September 1997 Application for Amend to License NPF-43,relocating Selected Requirements & Associated Bases from TS to Ufsar.Rev of TS Index & List of Tables to Reflect Relocation Requested NRC-97-0107, Application for Amend to License NPF-43,adding Special Test Exception to Allow Unit to Remain in Operational Condition 4 W/Reactor Coolant Temps Greater than 200 F,But Less than 212 F,When Performing Inservice Leak & Hydrostatic Testing1997-09-0505 September 1997 Application for Amend to License NPF-43,adding Special Test Exception to Allow Unit to Remain in Operational Condition 4 W/Reactor Coolant Temps Greater than 200 F,But Less than 212 F,When Performing Inservice Leak & Hydrostatic Testing NRC-97-0037, Application for Amend to License NPF-43,relocating Surveillance Requirements for Reactor Recirculation Sys MG Set Scoop Tube Stop Setpoints to UFSAR1997-06-20020 June 1997 Application for Amend to License NPF-43,relocating Surveillance Requirements for Reactor Recirculation Sys MG Set Scoop Tube Stop Setpoints to UFSAR NRC-97-0031, Application for Amend to License NPF-43,requesting Elimination of Selected Response Time Testing Requirements1997-03-27027 March 1997 Application for Amend to License NPF-43,requesting Elimination of Selected Response Time Testing Requirements NRC-96-0134, Application for Amend to License NPF-43,modifying TS Section 3.1.4.3,Table 3.3.6-1 & Table 4.3.6-1 Re Rod Block Monitor Applicability1996-12-0202 December 1996 Application for Amend to License NPF-43,modifying TS Section 3.1.4.3,Table 3.3.6-1 & Table 4.3.6-1 Re Rod Block Monitor Applicability ML20129F0611996-09-25025 September 1996 Application for Amend to License NPF-43,revising Tech Spec 4.8.4.3 Re Periodic Testing Requirement for Thermal Overload Protection Devices NRC-96-0075, Application for Amend to License NPF-43,changing SLMCPRs in TS 2.1.2 to Reflect Results of cycle-specific Calculation Performed for Plant Operating Cycle 6 Expected to Commence in 1996 & Deleting Specific SLMCPR Value1996-09-0505 September 1996 Application for Amend to License NPF-43,changing SLMCPRs in TS 2.1.2 to Reflect Results of cycle-specific Calculation Performed for Plant Operating Cycle 6 Expected to Commence in 1996 & Deleting Specific SLMCPR Value NRC-96-0003, Application for Amend to License NPF-43,modifying Charcoal Testing Stds for Control Room Emergency Filtration Sys & Standby Gas Treatment Sys1996-03-25025 March 1996 Application for Amend to License NPF-43,modifying Charcoal Testing Stds for Control Room Emergency Filtration Sys & Standby Gas Treatment Sys ML20095K4211995-12-21021 December 1995 Application for Amend to License NPF-43,incorporating 10CFR50,App J,Option B NRC-95-0124, Application for Amend to License NPF-43,modifying TS Action Statements 3.8.1.1.b & 3.8.1.1.d,SRs 4.8.1.1.2.a,4.8.1.1.3 & 4.8.1.2,Table 4.8.1.1.2-1 & Bases 3/4.8.1,3/4.8.2 & 3/4.8.31995-11-22022 November 1995 Application for Amend to License NPF-43,modifying TS Action Statements 3.8.1.1.b & 3.8.1.1.d,SRs 4.8.1.1.2.a,4.8.1.1.3 & 4.8.1.2,Table 4.8.1.1.2-1 & Bases 3/4.8.1,3/4.8.2 & 3/4.8.3 NRC-95-0104, Application for Amend to License NPF-43,incorporating one- Time Deferral of Limited Aspects of SR 4.3.3.2,4.8.1.1.2.e. 4.b & 4.8.1.1.2.e.6.b Into Plant TS1995-10-0202 October 1995 Application for Amend to License NPF-43,incorporating one- Time Deferral of Limited Aspects of SR 4.3.3.2,4.8.1.1.2.e. 4.b & 4.8.1.1.2.e.6.b Into Plant TS NRC-95-0096, Application for Amend to License NPF-43,revising TS Re Sys Testing,Instrumentation Calibr,Component Insp,Component Testing,Response Time Testing & Logic Sys Functional Tests to Allow one-time Extension of Surveillance Intervals1995-09-20020 September 1995 Application for Amend to License NPF-43,revising TS Re Sys Testing,Instrumentation Calibr,Component Insp,Component Testing,Response Time Testing & Logic Sys Functional Tests to Allow one-time Extension of Surveillance Intervals NRC-94-0107, Application for Amend to License NPF-43,proposing Changes to Administrative Controls Section of Ts,Consistent W/Guidance in NUREG-1433 & GL 93-07, Mod of Ts...For Emergency & Security Plans1994-12-15015 December 1994 Application for Amend to License NPF-43,proposing Changes to Administrative Controls Section of Ts,Consistent W/Guidance in NUREG-1433 & GL 93-07, Mod of Ts...For Emergency & Security Plans NRC-94-0047, Application for Amend to License NPF-43,incorporating Changes to Ts,Removing Component Lists from TS Sections 3.6.3 & 3.8.4.3 Per GL 91-081994-05-10010 May 1994 Application for Amend to License NPF-43,incorporating Changes to Ts,Removing Component Lists from TS Sections 3.6.3 & 3.8.4.3 Per GL 91-08 NRC-94-0027, Application for Amend to License NPF-43,relocating Response Time Limit Tables from TS to Ufsar,In Response to GL 93-08 & BWROG Topical Rept NEDO-322911994-04-26026 April 1994 Application for Amend to License NPF-43,relocating Response Time Limit Tables from TS to Ufsar,In Response to GL 93-08 & BWROG Topical Rept NEDO-32291 NRC-93-0151, Application for Amend to License NPF-43 Re Reduced Testing During Power Operation1994-03-29029 March 1994 Application for Amend to License NPF-43 Re Reduced Testing During Power Operation NRC-93-0143, Application for Amend to License DPR-9,revising TS for Implementation of Revised 10CFR20 Requirements1993-12-0909 December 1993 Application for Amend to License DPR-9,revising TS for Implementation of Revised 10CFR20 Requirements NRC-93-0077, Application for Amend to License NPF-43.Amend Provides Updated Lab Testng Standard for Surveillance Testing of Activated Charcoal Samples from Control Room Emergency Filtration Sys1993-07-29029 July 1993 Application for Amend to License NPF-43.Amend Provides Updated Lab Testng Standard for Surveillance Testing of Activated Charcoal Samples from Control Room Emergency Filtration Sys NRC-93-0061, Application for Amend to License NPF-43,revising TS to Extend Instrument Calibr Intervals to 36 Months for Selected Instrumentation,Per BWROG Licensing Topical Rept NEDC-32160P,Dec 1992.GE Proprietary Rept Encl.Rept Withheld1993-07-29029 July 1993 Application for Amend to License NPF-43,revising TS to Extend Instrument Calibr Intervals to 36 Months for Selected Instrumentation,Per BWROG Licensing Topical Rept NEDC-32160P,Dec 1992.GE Proprietary Rept Encl.Rept Withheld NRC-93-0078, Application for Amend to License NPF-43,changing TS 6.8.5.e to Provide Proper Refs to 10CFR20 as Result of New Section Numbers1993-07-29029 July 1993 Application for Amend to License NPF-43,changing TS 6.8.5.e to Provide Proper Refs to 10CFR20 as Result of New Section Numbers NRC-93-0062, Application for Amend to License NPF-43,changing Tech Specs Include Modification to Job Titles Following Mgt Reorganization,Changes to Onsite Review Organization Membership Description & Change to Overtime Requirements1993-05-24024 May 1993 Application for Amend to License NPF-43,changing Tech Specs Include Modification to Job Titles Following Mgt Reorganization,Changes to Onsite Review Organization Membership Description & Change to Overtime Requirements NRC-93-0038, Application for Amend to License NPF-43,modifying Leakage Testing Requirements for Primary Containment Isolation Valves in Injection Flow Paths of LPCI Mode of RHR Sys1993-05-24024 May 1993 Application for Amend to License NPF-43,modifying Leakage Testing Requirements for Primary Containment Isolation Valves in Injection Flow Paths of LPCI Mode of RHR Sys 1999-09-24
[Table view] Category:TEXT-LICENSE APPLICATIONS & PERMITS
MONTHYEARML20217N4301999-10-25025 October 1999 Amend 17 to License DPR-9,revising TS by Deleting SR D.3.c, Which Required Weekly Observation of Nitrogen Cover Gas Pressure within Sodium Storage Tanks Located in Sodium Building NRC-99-0082, Application for Amend to License NPF-43,revising TS 3/4.6.1.8 to Allow Continued Operation Until Next Plant Shutdown at Which Time Valve T4803F601 Will Be Repaired1999-09-24024 September 1999 Application for Amend to License NPF-43,revising TS 3/4.6.1.8 to Allow Continued Operation Until Next Plant Shutdown at Which Time Valve T4803F601 Will Be Repaired NRC-99-0072, Application for Amend to License NPF-43,revising SRs & Bases for Div I Battery Sys to Agree with Design of New Battery Replacement1999-09-10010 September 1999 Application for Amend to License NPF-43,revising SRs & Bases for Div I Battery Sys to Agree with Design of New Battery Replacement NRC-99-0078, Rev 14 to Application for Amend to License NPF-43,providing Update for Remaining Open Issues Associated with NRC Review of ITS Submittal.Brief Abstract of Changes Included in Rev & Revised Pages for Submittal & Rev Instructions,Included1999-08-25025 August 1999 Rev 14 to Application for Amend to License NPF-43,providing Update for Remaining Open Issues Associated with NRC Review of ITS Submittal.Brief Abstract of Changes Included in Rev & Revised Pages for Submittal & Rev Instructions,Included NRC-99-0048, Application for Amend to License NPF-43 to Change TS to Include Provisions for Enabling Oscillation Power Range Monitor (OPRM) Upscale Function in Average Power Range Monitor (Aprm).Draft TS Pages Encl1999-07-30030 July 1999 Application for Amend to License NPF-43 to Change TS to Include Provisions for Enabling Oscillation Power Range Monitor (OPRM) Upscale Function in Average Power Range Monitor (Aprm).Draft TS Pages Encl NRC-99-0035, Application for Amend to License DPR-9 to Modify TS Section D.3.Amend Would Eliminate TS Surveillance Requirement for Ni Cover Gas on Nearly Empty Primary Sodium Storage Tanks in Sodium Bldg Complex.With marked-up & Typed TS Pages1999-04-20020 April 1999 Application for Amend to License DPR-9 to Modify TS Section D.3.Amend Would Eliminate TS Surveillance Requirement for Ni Cover Gas on Nearly Empty Primary Sodium Storage Tanks in Sodium Bldg Complex.With marked-up & Typed TS Pages ML20205Q7091999-04-15015 April 1999 Amend 16 to License DPR-9,allowing Possession of Nominal Amount of Special Nuclear Matl NRC-99-0025, Application for Amend to License NPF-43,modifying TS SR 4.4.1.1.1 to Require Each Recirculation Pump Discharge Valve Be Demonstrated Operable at Least Once Every 18 Months & Deleting Footnote That Applies to TS 4.4.1.1.11999-03-23023 March 1999 Application for Amend to License NPF-43,modifying TS SR 4.4.1.1.1 to Require Each Recirculation Pump Discharge Valve Be Demonstrated Operable at Least Once Every 18 Months & Deleting Footnote That Applies to TS 4.4.1.1.1 ML20198S3271999-01-0606 January 1999 Amend 15 to License DPR-9,consisting of Changes to TS ML20154R2251998-10-21021 October 1998 Amend 13 to License DPR-9,allowing Access Control Flexibility,Establishing Compensatory Provisions Re PA Boundary,Eliminating Redundancy Between Ts,Revising Figure B-1 & Correcting Typos NRC-98-0122, Rev 1 to 980403 Application for Amend to License NPF-43, Proposing TS Change for Conversion to Improved Standard Ts. Revised Pages for Submittal & Brief Abstract of Changes, Encl1998-09-28028 September 1998 Rev 1 to 980403 Application for Amend to License NPF-43, Proposing TS Change for Conversion to Improved Standard Ts. Revised Pages for Submittal & Brief Abstract of Changes, Encl NRC-98-0128, Rev to 980128 Application for Amend to License DPR-9, Revising TS to Implement Provisions of 1996 Decommissioning Rule,Including Requirements for Control of Effluents,Dose Limits & Annual Reporting of 10CFR50.36a1998-08-26026 August 1998 Rev to 980128 Application for Amend to License DPR-9, Revising TS to Implement Provisions of 1996 Decommissioning Rule,Including Requirements for Control of Effluents,Dose Limits & Annual Reporting of 10CFR50.36a NRC-98-0117, Application for Amend to License NPF-43,revising Table 4.0.2-1 to Include Two Functional Units for TS 4.3.1.3 (RPS Response Time Testing) & Allowing one-time Extension of Respective Surveillance Intervals1998-07-23023 July 1998 Application for Amend to License NPF-43,revising Table 4.0.2-1 to Include Two Functional Units for TS 4.3.1.3 (RPS Response Time Testing) & Allowing one-time Extension of Respective Surveillance Intervals NRC-98-0044, Application for Amend to License DPR-9,allowing Util to Possess Special Nuclear Matl in Quantity Totaling No More than 15 Grams of U-235,U-233 or Pu,Or Any Combination Thereof,W/Pu Activity Totaling No More than 2 Ci1998-07-17017 July 1998 Application for Amend to License DPR-9,allowing Util to Possess Special Nuclear Matl in Quantity Totaling No More than 15 Grams of U-235,U-233 or Pu,Or Any Combination Thereof,W/Pu Activity Totaling No More than 2 Ci NRC-98-0040, Application for Amend to License NPF-43,requesting to Allow one-time Extension of Surveillance Intervals to Delay Shutdown for Upcoming Sixth Refueling Outage (RFO6) Until 9809041998-06-26026 June 1998 Application for Amend to License NPF-43,requesting to Allow one-time Extension of Surveillance Intervals to Delay Shutdown for Upcoming Sixth Refueling Outage (RFO6) Until 980904 ML20248L7981998-06-0505 June 1998 Application for Amend to License NPF-43,revising TS Section 2.1.2.Proprietary & non-proprietary Info,Encl.Proprietary Info Withheld NRC-98-0065, Application for Amend to License NPF-43,to Add Configuration Risk Mgt Program to TS Section 6.8.5,contingent on Approval of Previously Submitted License Amend for TS 3.8.1.11998-04-27027 April 1998 Application for Amend to License NPF-43,to Add Configuration Risk Mgt Program to TS Section 6.8.5,contingent on Approval of Previously Submitted License Amend for TS 3.8.1.1 NRC-98-0071, Application for Amend to License NPF-43,proposing Align Shutdown Action Statements for Primary Containment Oxygen Monitoring Instrumentation in Three Specifications1998-04-0909 April 1998 Application for Amend to License NPF-43,proposing Align Shutdown Action Statements for Primary Containment Oxygen Monitoring Instrumentation in Three Specifications NRC-98-0043, Application for Amend to License NPF-43 to Convert Current TS to Improved Ts.Meeting Is Requested to Discuss Review Schedule & Contents of Amend.Vol 1 Includes Application & Justification.Vols 2-13 Contain Improved TS1998-04-0303 April 1998 Application for Amend to License NPF-43 to Convert Current TS to Improved Ts.Meeting Is Requested to Discuss Review Schedule & Contents of Amend.Vol 1 Includes Application & Justification.Vols 2-13 Contain Improved TS NRC-98-0062, Application for Amend to License NPF-43,modifying Drywell Oxygen Monitoring Instrumentation Action Requirements to Be Consistent W/Those Contained in NUREG-1433,Rev 1, STS GE Plants,BWR/41998-04-0202 April 1998 Application for Amend to License NPF-43,modifying Drywell Oxygen Monitoring Instrumentation Action Requirements to Be Consistent W/Those Contained in NUREG-1433,Rev 1, STS GE Plants,BWR/4 NRC-98-0057, Application for Amend to License NPF-43,revising Requirements Associated W/Containment Oxygen & Hydrogen Monitors1998-04-0202 April 1998 Application for Amend to License NPF-43,revising Requirements Associated W/Containment Oxygen & Hydrogen Monitors NRC-98-0033, Application for Amend to License NPF-43,eliminating Incorrect Descriptive Info Re Water Inventory in CST Reserved for Hpci/Rcic & Raising CST Min Water Level for Core Spray1998-03-27027 March 1998 Application for Amend to License NPF-43,eliminating Incorrect Descriptive Info Re Water Inventory in CST Reserved for Hpci/Rcic & Raising CST Min Water Level for Core Spray NRC-98-0034, Application for Amend to License NPF-43,revising Footnote Specifying Conditions Where Isolation Valves Associated W/ LPCI Sys Operation Are Repositioned1998-03-27027 March 1998 Application for Amend to License NPF-43,revising Footnote Specifying Conditions Where Isolation Valves Associated W/ LPCI Sys Operation Are Repositioned NRC-98-0003, Application for Amend to License NPF-43,revising Tech Specs to Improve Administrative Controls Re thermal-hydraulic Stability & Idle Recirculation Loop Startup & Eliminating Neutron Flux Indication from TS1998-01-28028 January 1998 Application for Amend to License NPF-43,revising Tech Specs to Improve Administrative Controls Re thermal-hydraulic Stability & Idle Recirculation Loop Startup & Eliminating Neutron Flux Indication from TS NRC-98-0027, Application for Amend to License DPR-6,modifying Sections F & I of Plant TS to Include Requirements for Control of Effluents,Dose Limits & Annual Reporting Per 10CFR50.36a1998-01-28028 January 1998 Application for Amend to License DPR-6,modifying Sections F & I of Plant TS to Include Requirements for Control of Effluents,Dose Limits & Annual Reporting Per 10CFR50.36a NRC-98-0006, Application for Amend to License NPF-43,changing Surveillance Interval in TS 4.4.3.2.2.a by Extending It from Current 18 Month Testing Interval to 24 Month Testing Interval to Be Consistent W/Asme Code Requirements1998-01-28028 January 1998 Application for Amend to License NPF-43,changing Surveillance Interval in TS 4.4.3.2.2.a by Extending It from Current 18 Month Testing Interval to 24 Month Testing Interval to Be Consistent W/Asme Code Requirements NRC-98-0002, Application for Amend to License NPF-43,revising SRs for Div II Battery Sys to Agree W/Design of New Battery Replacement1998-01-28028 January 1998 Application for Amend to License NPF-43,revising SRs for Div II Battery Sys to Agree W/Design of New Battery Replacement NRC-98-0008, Application for Amend to License NPF-43,revising Footnotes Specifying Conditions Under Which SRs Associated W/Ts 3/4.9.1, Reactor Mode Switch, Can Be Performed1998-01-28028 January 1998 Application for Amend to License NPF-43,revising Footnotes Specifying Conditions Under Which SRs Associated W/Ts 3/4.9.1, Reactor Mode Switch, Can Be Performed NRC-98-0023, Application for Amend to License DPR-9,allowing Util to Possess Contaminated Apparatus & Equipment & Radioactive Sources at Fermi 1 Containing Byproduct Matl Not Produced by Operation of Plant Reactor1998-01-28028 January 1998 Application for Amend to License DPR-9,allowing Util to Possess Contaminated Apparatus & Equipment & Radioactive Sources at Fermi 1 Containing Byproduct Matl Not Produced by Operation of Plant Reactor NRC-98-0025, Application for Amend to License DPR-9,changing TS on Access Control to Provide Flexibility While Maintaining Similar Controls Over Access1998-01-28028 January 1998 Application for Amend to License DPR-9,changing TS on Access Control to Provide Flexibility While Maintaining Similar Controls Over Access NRC-97-0115, Application for Amend to License DPR-9,modifying Part 2.A in Order to Delete Reference to Six Letters Now Listed & Instead Refer to Encl Fermi 1 SAR1997-12-15015 December 1997 Application for Amend to License DPR-9,modifying Part 2.A in Order to Delete Reference to Six Letters Now Listed & Instead Refer to Encl Fermi 1 SAR NRC-97-0105, Application for Amend to License NPF-43,revising TS to Be Consistent W/Planned Replacement of Current Power Range Monitoring Portion of Existing Nms1997-12-10010 December 1997 Application for Amend to License NPF-43,revising TS to Be Consistent W/Planned Replacement of Current Power Range Monitoring Portion of Existing Nms ML20211J1971997-09-29029 September 1997 Application for Amend to License NPF-43,relocating Selected Requirements & Associated Bases from TS to Ufsar.Rev of TS Index & List of Tables to Reflect Relocation Requested NRC-97-0107, Application for Amend to License NPF-43,adding Special Test Exception to Allow Unit to Remain in Operational Condition 4 W/Reactor Coolant Temps Greater than 200 F,But Less than 212 F,When Performing Inservice Leak & Hydrostatic Testing1997-09-0505 September 1997 Application for Amend to License NPF-43,adding Special Test Exception to Allow Unit to Remain in Operational Condition 4 W/Reactor Coolant Temps Greater than 200 F,But Less than 212 F,When Performing Inservice Leak & Hydrostatic Testing NRC-97-0037, Application for Amend to License NPF-43,relocating Surveillance Requirements for Reactor Recirculation Sys MG Set Scoop Tube Stop Setpoints to UFSAR1997-06-20020 June 1997 Application for Amend to License NPF-43,relocating Surveillance Requirements for Reactor Recirculation Sys MG Set Scoop Tube Stop Setpoints to UFSAR NRC-97-0031, Application for Amend to License NPF-43,requesting Elimination of Selected Response Time Testing Requirements1997-03-27027 March 1997 Application for Amend to License NPF-43,requesting Elimination of Selected Response Time Testing Requirements ML20133L6171997-01-0202 January 1997 Amend 11 to License DPR-9,allowing Certain Equipment & Instruments to Be Removed from Svc for Short Periods of Time Allowing for Maint,Testing,Insp & Account for Equipment Failures NRC-96-0134, Application for Amend to License NPF-43,modifying TS Section 3.1.4.3,Table 3.3.6-1 & Table 4.3.6-1 Re Rod Block Monitor Applicability1996-12-0202 December 1996 Application for Amend to License NPF-43,modifying TS Section 3.1.4.3,Table 3.3.6-1 & Table 4.3.6-1 Re Rod Block Monitor Applicability ML20129F0611996-09-25025 September 1996 Application for Amend to License NPF-43,revising Tech Spec 4.8.4.3 Re Periodic Testing Requirement for Thermal Overload Protection Devices NRC-96-0075, Application for Amend to License NPF-43,changing SLMCPRs in TS 2.1.2 to Reflect Results of cycle-specific Calculation Performed for Plant Operating Cycle 6 Expected to Commence in 1996 & Deleting Specific SLMCPR Value1996-09-0505 September 1996 Application for Amend to License NPF-43,changing SLMCPRs in TS 2.1.2 to Reflect Results of cycle-specific Calculation Performed for Plant Operating Cycle 6 Expected to Commence in 1996 & Deleting Specific SLMCPR Value NRC-96-0003, Application for Amend to License NPF-43,modifying Charcoal Testing Stds for Control Room Emergency Filtration Sys & Standby Gas Treatment Sys1996-03-25025 March 1996 Application for Amend to License NPF-43,modifying Charcoal Testing Stds for Control Room Emergency Filtration Sys & Standby Gas Treatment Sys ML20095K4211995-12-21021 December 1995 Application for Amend to License NPF-43,incorporating 10CFR50,App J,Option B NRC-95-0124, Application for Amend to License NPF-43,modifying TS Action Statements 3.8.1.1.b & 3.8.1.1.d,SRs 4.8.1.1.2.a,4.8.1.1.3 & 4.8.1.2,Table 4.8.1.1.2-1 & Bases 3/4.8.1,3/4.8.2 & 3/4.8.31995-11-22022 November 1995 Application for Amend to License NPF-43,modifying TS Action Statements 3.8.1.1.b & 3.8.1.1.d,SRs 4.8.1.1.2.a,4.8.1.1.3 & 4.8.1.2,Table 4.8.1.1.2-1 & Bases 3/4.8.1,3/4.8.2 & 3/4.8.3 NRC-95-0104, Application for Amend to License NPF-43,incorporating one- Time Deferral of Limited Aspects of SR 4.3.3.2,4.8.1.1.2.e. 4.b & 4.8.1.1.2.e.6.b Into Plant TS1995-10-0202 October 1995 Application for Amend to License NPF-43,incorporating one- Time Deferral of Limited Aspects of SR 4.3.3.2,4.8.1.1.2.e. 4.b & 4.8.1.1.2.e.6.b Into Plant TS NRC-95-0096, Application for Amend to License NPF-43,revising TS Re Sys Testing,Instrumentation Calibr,Component Insp,Component Testing,Response Time Testing & Logic Sys Functional Tests to Allow one-time Extension of Surveillance Intervals1995-09-20020 September 1995 Application for Amend to License NPF-43,revising TS Re Sys Testing,Instrumentation Calibr,Component Insp,Component Testing,Response Time Testing & Logic Sys Functional Tests to Allow one-time Extension of Surveillance Intervals NRC-94-0107, Application for Amend to License NPF-43,proposing Changes to Administrative Controls Section of Ts,Consistent W/Guidance in NUREG-1433 & GL 93-07, Mod of Ts...For Emergency & Security Plans1994-12-15015 December 1994 Application for Amend to License NPF-43,proposing Changes to Administrative Controls Section of Ts,Consistent W/Guidance in NUREG-1433 & GL 93-07, Mod of Ts...For Emergency & Security Plans NRC-94-0047, Application for Amend to License NPF-43,incorporating Changes to Ts,Removing Component Lists from TS Sections 3.6.3 & 3.8.4.3 Per GL 91-081994-05-10010 May 1994 Application for Amend to License NPF-43,incorporating Changes to Ts,Removing Component Lists from TS Sections 3.6.3 & 3.8.4.3 Per GL 91-08 NRC-94-0027, Application for Amend to License NPF-43,relocating Response Time Limit Tables from TS to Ufsar,In Response to GL 93-08 & BWROG Topical Rept NEDO-322911994-04-26026 April 1994 Application for Amend to License NPF-43,relocating Response Time Limit Tables from TS to Ufsar,In Response to GL 93-08 & BWROG Topical Rept NEDO-32291 NRC-93-0151, Application for Amend to License NPF-43 Re Reduced Testing During Power Operation1994-03-29029 March 1994 Application for Amend to License NPF-43 Re Reduced Testing During Power Operation NRC-93-0143, Application for Amend to License DPR-9,revising TS for Implementation of Revised 10CFR20 Requirements1993-12-0909 December 1993 Application for Amend to License DPR-9,revising TS for Implementation of Revised 10CFR20 Requirements 1999-09-24
[Table view] |
Text
-
. p: ,
. s.caiph syh6 ?
e[][(
y S'a'o' v'c' P'8*'deat '-
M.b - uw wonn oe,. s,on..y . -
g-gg newport.wch.gan 4ew nia,5854i30 V ,
l 7
Novenber 16, 1989' NIC-89-0215 '
?
U. S. Maclear Regulatory Comnission Attn: Document Control Desk if ,
Washington,: D. C. 20555- I iDeferences: 1) Ft.stmi 2
- p. . N1C Docket No. 50-341
~
NIC License No. WF-43 i
~
- 2) Detroit Riison Letter to N10, _ NIC-89-0209,
" Control Room Emergency Filtration System,
, License Condition", dated Septenber 27, 1989 3)- Detroit R11 son Ietter to NIC, NRC-88-0185, -i Y '
_" Proposed-Technical Specification Change ,
(License Amendment) - Control Boom ' ,
Emergency Filtration System'(3/4.7.2)", i dated December 22, 1988-- -
-4) -Detroit! Riison Letter to NIC, EP2-72039,
" Clarification of Position on Silicone Duct Sealant and Other Issues", dated '
January 8, 1985
Subject:
Proposed Technical Specification Change (License Amendment) - Control Room Bnergency Filtration Systen (3/4.7.2)
Pursuant.to 10CFR50.90, Detroit Fdison Conpany hereby proposes to
' amend Operating License WF-43 for the Fermi 2 plant by incorporating the enclosed changes into the Plant Technical Specifications. The L 2 proposed changes provide surveillance requirements for periodic
? leakage testing-and visual inspection of the Control Rom Emergency L Filtration System to assure the integrity of those portions of the l
. system external to the Control Rom. This application for amendment j is' submitted pursuant to License Condition 2.C(7) of the Fermi 2 ;
. Operating Licenm and satisfies the requirements of this License '
Condition. c'Iherefore, the deletion of License Condition 2.C(7) is
?- included in this proposal.
' Detroit Edison has evaluated the proposed Technical Specifications
~
!i ~ l against the criteria of 10CFR50.92 and determined that no significant l- hazards consideration is involved. The Fermi 2 Onaite Review Organization has approved and the Nuclear Safety Review Group has L:'
l reviewed the pr enclosed determ sed Technical Specifications and concurs with the tions. In accordance with 10CFR50.91, Detroit h,j l-R11 son has provided a copy of this letter to the State of Michigan. /30 t 8912010027 891116
- -;s ' _ , s en .,
i: ,
^.
'-g 'USNBC.L
=Novenber-16,.1989.
g:. <
NRC-89-0215 Page;2-i l
If you have any questions, please' contact Mr. Glen Ohlemacher at (313) i
- 586-4275.. ,
Sincerely '
x -
h;
'Ehclosure.
, cc: -A. B. Davis-Y R.' W.~Defayette
- W. .G.~ Rogers - '
J. F. Stang Supervisor, Myanced Planning and Review Section, *
^
Michigan Public Service Ccannission '
fy l e l ,
m.
I t-i i
Y ,
7,. s
~
l' y
-S ,. ..USNRC .
Novenber 16, 1989 L~,. NRC-89-0215- ,
Page 3 ,
t t
I, B. RALPH SYLVIA, do hereby affirm that the. foregoing statenents are based on facts and circunstances which are true and accurate to the best of my knowledge and belief.
rO4b /o
'B. RAIMH SpVIA Senior Vice President On this / day of IVda (L- , 1989, before me -i personally appeared B. Ralph Sylfia, being first duly sworn and says c
' that he execute:1 the foregoing as his free act and deed.
I ba& G. Aurdb Notary Public '
ROSAUE A ARMETTA Notary Publ:c. Morvoe County, Mi MyCommlulon ExpkosJan.11,1992
-.-a* - - - - - - - - - . . - - - - - - - - . - - - - . , , , .
Q
. e 'i
~
.c; .Enclo:ura to i 4' WRC-89-0215 E ' ,
Page:1- 1 n ;-
INTRODUCTION During the initial licensing of Fermi 2, concerns about the use of silicone sealant on duct. work in the Control Room Emergency Filtration System (CREFS) outside of the main control room zone were raised by the NRC. The concerns dealt with the ability of the silicone sealant to perform its sealing function over the designed plant lifetime of 40 ,
+
' years. The resolution of these concerns,-which are discussed in detail in Section'6.4.1 of the Fermi 2 Safety Evaluation Report (NUREG-0798) Supplements 5 and 6 (SSER 5 and 6), resulted in the issuance of'the Fermi-2 Operating License (NPF-43) with Condition ,
2.C(7). i
' Condition 2.C(7.) reads as follows:
(7) Control Room Habitability (Section 6.4.1, SSER #6)
Prior to startup following the first refueling outage, DECO shall provide assurance to the NRC staff that potential contamination ,
pathways-through those portions of the control room air-conditioning system which are external to the control room zone will not have a significant adverse impact on control room habitability, or will propose a technical specification which provides for periodic leakage testing to assure-the integrity of those external portions of the control room air-conditioning 7 l
system.
As discussed in Reference 2, Detroit Edison has decided to follow the option provided in the License Condition to propose a Technical Specification for periodic leakage testing. This proposal provides the required Technical Specification.
l l;.
i
D
~
p
, L 5; ' Enclosure to-t, : ,
NRC-89-0215-Page_2
- To provide additional assurance that unexpected degradation of the silicone does not occur between leakage tests, Detroit Edison is proposing ~a surveillance requirement for visual inspection of accessible portions of the ductwork of concern.- .'The proposed surveillance will require an annual inspection to verify that the silicone sealant has not undergone cracking, debonding, or other abnormal degradation.
This proposal satisfies'the provisions of License Condition 2.C(7).
Therefore, deletion of this condition from the license is proposed.
EVALUATION The proposed periodic leakage test surveillance requirement consists of three parts. These are: test method, acceptance criteria, and test frequency. Each aspect is evaluated individually below. The proposed visual inspection requirements are evaluated in conjunction with the discussion of the proposed leakage test frequency.. l l4 i Test Method i
The proposed duct leakage testing is specified to be performed in accordance with ANSI N510-1980. This document provides the industry standards for the testing of emergency filtration systems at nuclear ;
power plants. Included are acceptable methods for duct leak testing.
Since ANSI N510-1980 provides the most recent industry standard for i
testing of the type proposed, Detroit Edison believes it is acceptable i to reference the standard in this surveillance requirement. Further, j.
this is consistent with other CREFS surveillance requirements, such as system flow rate verification, which reference ANSI N510-1980. -l l
y ;: 3 Enclosure to g
NRC-89-0215 Page 3 The surveillance requirement must also specify the test pressures of concern. In this case, there are four ducts of concern. Each duct
! must be tested at two pressures; one pressure represents the maximum negative pressure expected for that duct during normal system operation, the other pressure represents the aaximum negative presrure expected for that duct during operation with a single failure of a damper. The single damper failure chosen is the one that results in i" the greatest negative pressure in all four ducts of concern. These test conditions, rather than the specific pressuri:s for each duct, are listed in the Specification. Specifying that the test pressures be at or mere negative than the maximum negative pressure expected for each of the four specific duct sections of concern during normal system operation and during operation with a single damper failure assures that the tests will be conducted at the appropriate pressures while eliminating the need for future Technical Specification changes if the normal operating pressure in a specific duct changes over tr life of the plant. The calculations performed for test pressures for the first refueling outage are contained in Attachment 1.
M eytance Criteria i
Leakage into the subject ducts would provide a path of unfiltered air
( inleakage into the Control Room. Currently, the calculations for b radiological dose to Control Room personnel assume a 10 standard cubic foot per minute (sofm) inleakage from all sources averaged over the j 30-day period. This calculation, as documented in Section 6.4.1 of SSERS, resulted in a dose of 16.1 rem to the thyroid, which is well below the criteria of General Design Criteria (GDC) 19 of 10CFR50 Appendix A. The GDC 19 criteria is 5 rem whole body exposure or the equivalent. The NRC Standard Revir- Slan (NUREG-0800') Section 6.4
3
, Enclosure to t, NRC-89-0215 Page 4 provides 30 ren thyroid dose as a standard for meeting the GDC 19 criteria.
To support the establishment of appropriate acceptance criteria for this surveillance requirement, Detroit Edison has recalculated the dose to the Control Room personnel besed upon new unfiltered air inleakage assumptions. The same methodology and other assumptions used by the NRC staff in the pre-operating license review were used in
~
these calculations, with the exception of the dose conversion factors for iodine. The more recently established values were used, which are contained in Regulatory Guide 1.109, Revision 1, October 1977.
Details on the dose calculation are found in the attached Design Calculation 5107 (Attachment 2).
In addition to unfiltered inleakage due to duct leakage, unfiltered air may enter the Control Room due to the openings of Control Room doors for ingress and egress during the 30-day period. The Fermi 2 Control Room has vestibules installed in the doorways which are used for normal ingre,s and egress. Although other doors penetrate the Control Room envelope, these doors would not normally be used under accident conditions. Detroit Edison has determined that a leakage of 1.0 sofm average 6 over the 30-day period can be conservatively assigned to the opening of Control Room access doors. This is based upon calculations of air exchange during periodic use of the doors.
The Fermi 2 CREFS consists of redundant, divisional, fans and dampers and non-redundant passive flow paths. The failure of a damper can cause significantly increased negative pressures in the subject ductwork. However, this occurrence will be readily detected by the Control Room operator from Control Room indication and alarms. For this reason, the duration of CREFS operation in this " failure mode" is
r 7 i Enr.losure to
(* NRC-89-0215 Page 5 limited to 30 ainutes. At that time it is assumed that the operator shifts to the operable division of the CREFS. The calculations performed assume the single damper failure occurs at the worst point f in the scenarios which is at the time of accident initiation. i The Fermi 2 accident analysis, in general, allows credit to be taken for operator action following time periods ranging from 10 minutes to 30 minutes. For conservatism, 30 ainutes is designated as the time :
required for the operator to detect the damper failure and shift CREFS operation to the unaffected division of active components. ;
The revised control room dose calculations, which include the calculations for in-leakage for doors as well ac for duct in-leakage, are attached as Attachment 2. The assumed combined inleakage for the !
four ducts under both the normal and failure modes of CREFS operation l correspond to the acceptance criteria for the proposed leakage f testing.
Test Frequency Detroit Edison is proposing that this duct leakage testing be ;
performed at least once per 36 months. This interval corresponds to every second refueling outage. l In Reference 4, Detroit Edison provided the NRC staff with information concerning the properties of silicone sealant. This information included that silicone sealant has an expected 40-year life at 202 0F i and that the sealant is qualified for 1x107 rad environments. The temperature and radiation levels at Fermi 2 for this application are well below these levels.
i l
L
7- 3
. Enclosure to 4 .,.
NRC-89-0215 Page 6 In addition, two sections of the ductwork of concern were leak tested per ANSI N510-1980 in August 1984. The results, when compared to similar tests performed recently in October 1989, shows that the leakage characteristics of the ducts have not significantly changed in the intervening 62 months.
The above information indicates that, once tested, the ductwork and the associated sealant should be expected to maintain their integrity for the proposed 36 month surveillance test interval. However; the concern that, once the sealant reaches its end of life, the material will rapidly deteriorate must be addressed.
Firstly, the duct longitudinal seams fn question were braze welded prior to the application of the sealant. Tnus, the sealant acts as a backup to the wel*j and if the sealant completely failed the leakage characteristics of the ductwork is not expected to be apprecirSly changed. However, since the application of sealant was an accepted construction practice at the time of Fermi 2's construction, the ducts were never leak tested without the sealant applied. Consequently, the effect of complete sealant failure cannot be quantified.
1 For this reason, Detroit Edison is proposing an additional visual inspection program (Surveillance Requirement 4.7.2.2) for the silicone l
sealant on the ductwork of concern which is accessible during normal plant operation. This sealant will be visually inspected for 1
! deterioration annually. Since the accessible seams are representative of all the seams of concern (the environment of all seams is the same), the additional inspections will provide additional assurance that an onset of general deterioration of the silicorie sealant between tests does not go undetected.
l i-l
?
c Encionre to
- j. g NRC-89-0215
- j. Page 7 Since the appropriate course of action for a finding from these visual inspections depends on the nature of the finding, the proposed surveillance requires that the intended course of action be provided to the NRC staff in a Special Report within 134 days of the finding.
The nature of the finding could require a more prompt reporting requirement to be invoked, and any actions necessary to assure safe plant. operation will be taken regardless of the time frame for the' Special Report.
! Finally; if, notwithstanding the above, the leakage characteristics of the ductwork of concern were to deteriorate the following conservatisms exist to mitigate the consequences:
- 1) The ductwork of concern is located in the enclosed Auxiliary Building and is therefore not directly in the radioactive plume created by the accident scenario. (See Figure 1)
- 2) Some portions of the auctwork do not experience negative presuures unless significant filter loading occurs. This I condition is not expected to occur. L
- 3) There exists a margin of 11 3 rem to the thyroid between the i results of the new Control Room dose calculation (18.7 rem thyroid) and the GDC 19 criteria (30 rem thyroid).
, I For these reasons, Detroit Edison believes the proposed surveillance intervals to be acceptable.
i L
. ~ . . .
.. Enclosure to j i
t- ~ NRC-89-0215
' l Page 8 i
SIGIIFICANT HAZARDS CONSIDERATION j j
In accordance with 10CFR50 92, Detroit Edison has made a determination that the proposed amendment involves no significant hazards l considerations. To make this determination, Detroit Edison must j establish that operation in accordance with the proposed amendment i would not: 1) involve a significant increase in the probability or l
! 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 l aargin of safety.
The proposed change to include surveillance requirenents to assure the l integrity of those portions of the Control Room Emergency Filtration System (CREFS) external to the Control Room does not*
t i
- 1) Involve a significant increase in the probability or consequences ,
of an accident previously evaluated. The new surveillance ,
requirements act to give assurance that the radiation dose to Control Room personnel is maintained below the criteria of General Design Criteria (GDC) 19 of 10CFR50 Appendix A as t previously evaluated. As such, the change acts to ensure that ;
the consequences ot'previously evaluated accidents remain as ;
evaluated. The CREFS is not associated with any accident initiating mechanism; therefore, the probability of any previously evaluated accident is unchanged.
)
l
- 2) Create the possibility of a new or different kind of accident from any accident previously evaluated. The change provideS verification that passive features of the CREFS are not degrading. The proposed leakage test must be performed when the L
q ,,-,- - , - - - --y-w -- w - ,wm,- e - ,9
=
- .. Enclosure to :
t, , NRC-89-0215 !
Page 9
[
ductwork to be tested is permitted by the Technical i Specifications to be out-of-service, or the ACTION statement for j CREFS will apply. Therefore, the test does not affect the ;
ability of the CREFS to operate in the normal or emergency mode t when required. Conduct of the proposed inspections does not ]
! affect the normal or emergency modes of CREFS operation. The ,
proposal does not result in any modification of system or plant l design. Therefore, the proposal does not create any new accident initiating mechanisms.
- 3) Involve a significant reduction in a margin of safety. The ,
change assures that the radiation dose to Control' Room personnel- ]
during accident conditions remain below GDC 19 criteria over the l plant lifetime. In so doing, the change acts to maintain the margin of safety. !
Based on the above, Detroit Edison has d0termined that the proposed amendment does not involve a significe1t hazards consideration. ;
t ENVIRONMENTAL, IMPACT Detroit Edison has reviewed the proposed Technical Specification changes against the criteria of 10CFR51.22 for environmental j 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.
g v; y
e . Enclosure to i ,. NRC-89-0215 Page 10 00NCLilSION In Reference 3. Detroit Edison submitted a proposal to change the CREFS Technical Specification to make improvements in usability and clarity. The attached proposed Technical Specification change is based upon the current Fermi 2 Technical Specifications. The proposed Technical Specification changes for the Reference 3 proposal which includes the provisions of this proposal are also attached.
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.
[.
l l
j
A
+
l 1
4 FR.1ER UNrrs CCHVAC E'ONE O pg,,,
i ,~......s. . . .* fz. l
.l. :p ow s www=aes=mv
,/ ,1 1 154 .~:I I :
i .
= 1 ws ,
g -,
.; e, Koort i '
. 1 --1 1 yn. ! _
s rn w l
- ...,..,,......~...._s.,.,...- s.
. . s .. e . o . .* ", < . . l
\
erM l ~. IMTArc notTM(EM46[l l ) " SOUTH EMERGEMC1 !i i _f .
' '"' bb
? [ MAIN
' " R***
- i -
=..... . a, o. s e- s E connen. l
.: :. ...~. s.e 1 f ROOM NORMAL eMj l
?- i l RBat.VIMrs ,
t l ,- AND MORMAL % _ y '
EKHAosT *
' < \
s-I f , 3 no floon ^
- s. e e . s e s .. .. t e. ... < s e .e.s "fo. . ...e. * .% : . ; s' .e. s . 'u . *. s l =
[14AlW ENTRANCE N: .
wcTN VGS1*lBVLE FERMI-2 AUXIUARY i BUILO/WG FIGURE 1 i I
_ _ _ _ _ __ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _