Application for Amend to License DPR-9,reflecting Extension of Expiration Date for Possession Only License Until Mar 2025.Safety Evaluation & Status Description EnclML20127N337 |
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Fermi |
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05/15/1985 |
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Jens W DETROIT EDISON CO. |
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Shared Package |
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ML20127N333 |
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NUDOCS 8505230495 |
Download: ML20127N337 (19) |
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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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UNITED STATES'OF AMERICA BEFORE THE NUCLEAR REGULATORY COMMISSION
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.- In the matter of )
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THE DETROIT EDISON COMPANY ~) Docket No. 50-16
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.(Enrico Fermi Atomic Power )
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Plant Unit No. 1) )
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APPLICATION TO EXTEND LICENSE Pursuant to Section 50.90 of the Rules ~and Regulations of the Nuclear Regulatory Commission (" Commission"), the
~ Detroit Edison Company'(" Detroit Edison") requests the NRC to revise Edison's " Possession Only" License (License No.
L 52 {h 6 P
'Page 2 U
DRP-9) for Enrico Fermi l'to reflect an extension beyond the current expiration date.' The current Fermi License expires
. onLJune 30, 1985.-
_ .. Edison requests thatEthe License be extended for 40 years to
- expirelin March'2025,1at.which time it is~ currently intended that all : residual. activity. willi be removed and the License terminated. .The extension will allow Fermi-1 to be maintained in its present safe storage condition.
J
~ The extension will not.present a:significant hazards concern .,
as defined-in 10CFR50.92(c). The radiological. state of the
- facility"is becoming more progressively benign due to decay
- of residual radioactivity. Furthermore, the current ~
Technical Specifications provide for maintaining the.
4 facility in a manner that assures the health and safety of
~
the public will not be endangered. In adJition, no irreversible consequences are anticipated with the-extension. On the contrary, the extension-allows Detroit Edison the. option.to pursue the best available alternatives for the. final decommissioning of the facility. The safety evaluation in support of the application is included in AttachmentJ1.
1 i
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.:I. Pcge 3-
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T EThe presentEstatus of the-facility including description, .
- ' current radiation levels, surveillance program,
- administration and procedures are-delineated in Attachment 2 c in' support of this application.
i
'WHERFFORE, Applicants. request that the Possession Only.
License DRP-9 be extended as requested herein.
IN WITNESS WHEREOF, The-Detroit. Edison Company, has
- caused ~its name to be signed hereunto by its Vice President,
' Wayne H. Jens, this 20d day of May, 1985.
THE DETROIT EDI N COMPANY BY vv
. t: W. H. Jens Vice President Nuclear Operations
Pago 4
-I WAYNE-H. JENS, do hereby affirm that the foregoing 1
statements are based on the-facts and circumstances which-
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are-true and accurate to.the best of my knowledge and' belief.
/ -
dua WAYNE H. JENS Vice President Nuclear Operations On this e2e d day of , 1985, before me personally appeared Wayne H. Jens, being first duly sworn'and says that he executed the foregoing as his free act.and deed.
Notary Public MAftCIA BUCK Notary Public, Washtenaw County, MI My Commission Expires Dec.28,1987 Ar:g~ i W % .7E.
e 7
15 s
ATTACHMENT 1 - gAFETY EVALUATION
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~ SAFETY EVALUATION INTRODUCTION Retirement of the Fermi l plant was accomplished through provisions of 10CFR50.59 and through a series of Techni-
- cal Specification changes. The original decommission-
- ing plan submitted through ERDA document NP-20047, consisted of the following major elements
- 1. Shipping all fuel and blanket elements offsite.
- 2. Shipping all bulk radioactive and non-radioactive sodium offsite and passivating-the. residual sodium.
.3. Disposing of all other-contaminated or irradiated materials by shipping offsite or placing in restricted areas whose access is limited only to authorized personnel.
- 4. Securing some of the Reactor Building electrical, instrumentation, piping, ventilation, personnel'and equipment penetrations.
- 5. Sealing the primary system, comprised of the reactor vessel, primary sodium piping, primary shield tank, inachinery dome, primary sodium service,'and secondary sodium system out to welded pipe caps, and passivating the residual sodium-therein.
~6. Revising the site boundary to a very_ limited area to include.only those areas containing radioactivity.
- 7. Implementing a post-retirement surveillance plan.
All_ elements of the plan have been implemented with the shipment of primary sodium to the Argonne National Laboratory-West between October 29 and November 12, 1984.
The facility is currently in-a safe-storage condition.
Detroit Edison is proposing to continue maintaining the facility in its present condition until the_ year 2025 at which time all residual-radioactivity is currently intended to be removed and the License terminated. ,
e
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EVALUATION The radiological status of the facility is progressively becoming more benign due to the decay of residual radioactivity. In June 1973 the main source of
-radioactivity in the facility was estimated to be 1550 Curies, of which slightly more than 1500 Curies was due to Cobalt 60. The Cobalt 60 presently is calculated to have decayed to approximately 320 Curies, and by the year 2025, will have decayed to approximately lif Curies. Other contributors _ originally present such as Co-58, Fe-59 and Cr-51 are now essentially absent. The safe storage condition of the facility has been and will continue to be maintained on the basis of the Technical Specifications. This will assure that the barriers toresidual radioactivity will retain their physical integrity until such radioactivity is removed.
CONCLUSIONS Based on the above, the maintenance of the Fermi l facility in a safe storage condition until the year 2025 presents no increased risk to the-health and safety of the employees or the public, and is within the scope of current regulation. In addition, continued existence of the facility in the safe storage condition in accordance with the proposed amendment would not:
(1) involve a significant increase in the probability or consequences of an accident previously evaluated; or (2) create the possibility of a new or different kind of accident from any accident previously evaluated; or (3) involve a significant reduction in a margin of safety.
In addition, the proposed amendment creates no irrever-sible conditions. Options for final decommissioning of the facility remain open and flexible as the residual activity decreases.
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ATTACHMENT 2 - FERMI 1 STATUS DESCRIPTION L'
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, TABLE OF CONTENTS
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b I
1.0 INTRODUCTION
2.0 FACILITY DESCRIPTION 3.0 ADMINISTRATION a
4.0 ACCESS CONTROL 5.0 MONITORING AND ALARMS 6.0 SURVEYS, INSPECTIONS, AND TESTING 7.0 PROCEDURES 4
Table 1 Environmental Survey Regimes Figure 1 Facility Plan LBP/100/LIC-29/7.0
- 051785
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1.0 INTRODUCTION
(
The: retirement plan for: the Enrico Fermi 1 Power Plant .-was previously
' presented to lthe 'At'omic Energy Commission via a September 24, 1973 letter
- from'the Power Reactor Development Company. The following discussion is
- an J update ' ofithat information which reflects the' current status of Fermi 1.
As reflected in the September 24, 1973 submittal, the core fuel sections of all-214' Core A fuel' subassemblies ccaposed of'25.6 '/o enriched uranium
, - molybdenum alloy ~ were shipped to' the Savannah' River Plant facility for reprocessing.
The comp 1.ete inventory 'of approximately 70,000 gallons of primary sodium was stored. frozen in 1344, 50-gallon drums stored in .the reactor
' containment dome and..just. prior.to shipment, in the cask car trestleway.-
- This sodium was shipped to Argonne National Laboratory-West. between October
- 29.and November 12,1984. .Though virtually. all sodium has been. removed
'from the systems within Fermi 1, a ' residual heel of sodium (approximately 450 gallons estimated) is retained in vessels and piping formerly used for s odium.-
.The main source of activity in the facility, concentrated in the lower.
elevation' of the reactor building, was estimated in June 1973 to be 1550 -
curies, fof which slightly more than'1500 curies was due to cobalt 60.
present in the reactor support plates, holddown mechanism, and shield bars.
At the present time 'the Cobalt 60 is calculated to have decayed to approximately 320 curies, and in 2025, the time that " safe store" condition
- is
- Intended to. bef terminated, it will have decayed to approximately 1.6 curies. .0ther contributors present in 1973 (Co-58, Fe-59, and Cr-51) are -
!now essentially absent. Typical radiation levels'in the high radioactivity regions within the Protected Area presently average between-1.0 and 15 mres/hr. Areas outside the . protected area are at less than 5 microren/hr above natural background. . ,
The safe storage condition of the facility is maintained aon the basis of the Technical Specifications and the Administrative and Surveillance
~
Procedures which prescribe the' administration, access control, monitoring, periodic . environmental ~ and radiological surveys, long term maintenance
- provisions, and-record keeping requirements.
- 2.0 FACILITY DESCRIPTION'
.The Fermi 1 facility is located within the owner controlled area and outside' the protected area of. the nearby Fermi 2 Unit. Figure 1 presents -
- the' current facility plan. - ' As shown in the figure, the following buildings are-identified: ;
o Reactor Building
' The Reactor (or containment) Building contains, below floor, the empty
-radioactive reactor vessel (which itself is contained in the Primary Shield y Tank), . heat exchangers, primary sodium pumps, and the primary sodium i
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4 ' y oveEflow tank' (which has been passified and is open to the atmosphere). A moisture detector'is located in the area sump that alarms -in -the manned
' control station. Operators enter this area twice a year to check
.the moisture detector operation in accordance with the Technical S pec ifications. No moisture has been detected in this' area since the retirement. of the facility.
. Above ? floor level, the Reactor Building contains the machinery done, containment crane,-and other machinery. The primary system has' been capped
~
(with carbon dioxide- at 'approximately two inches water pressure. -Though virtually all sodium has been removed from~ the system an estimated 450
~
gallons of residual heel of sodium remains in the vessels or pipes formerly -
used for sodium. This residual- sodium contains an estimated 1.7 mci of Cs-137 and 0.34 aci of Sr-90.
The Reactor. Building outer' air lock door is kept' locked, except when occupied, to provide additional security. The interlock on the-emergency exit has been removed and the outer door can be operated from the inside in Lcase of'an emergency. -i o Fuel and Repair Building (FARB) -
This building houses 1 the fuel storage pool and fuel ' cut up pool which were
-drained out, cleaned and painted with strippable paint. In addition, above
' floor, .there is ' the sealed containment steam cleaning chamber and below.
. floor,Lthe sealed transfer. tank room, mechanical equipment room, liquid radioactive waste tank rooms , and the " hot" drains sump. . The transfer tank room houses a drained and sealed transfer tank containing a heel of passivated residual sodium.- The radioactive liquid waste tanks were originally drained. The " hot" sump has been left active. A moisture detector--in the sump alarms at the manual control station when water gets to the applicable level.- . The sump ' pumps presently pump into the liquid waste tanks, MK 7, 8, 9, or-15. In the last 10~ years, during which Fermi 1 has' been~ in a safe. storage condition, approximately 15,000 gallons of water have been discharged to the' tanks. The' quantity of liquid in the tanks is ,
. monitored from level indicators located in the upper floor of the Fuel and ,
Repair Building. - The total capacity of the tanks is 37,500. gallons..- - Much - l of.this water came from water in-leakage-from pipe penetrations to the
- Health Physics Building. The situation causing the in leakage has been corrected.
Radiation indications within the general area of the ground level floor of the Fuel and Repair' Building are below delectable levels. Slight contam-ination has been found in the fuel and cut-up pools and the " hot" sump.
As' of May '1985 the activity at the bottom of the sump pump was 100,000
- d pa/100cm2 and at the shaft of the pump was 20,000 dpm/100cm 2 . One corner of the bottom of the sump measured 15 mres/hr.
o Sodium Storage Building
~ The primary Sodium Storage Building contains three 15,000 gallon tanks.
The sodium in these tanks was removed and placed in 55 gallon drums. These
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. drums were shipped to Argonne National Laboratory-West in Idaho. The three primary sodium storage tanks have been passivated with a carbon dioxide cover gas which is maintained on the' tanks.
- Entrance to- the sodium tank room' is- through a steel door. in the north wall of the. building which has been locked.
- The Sodium-Storage Tank room was surveyed for radiation levels on April 15,
- 1985. The radiation-levels-between' tanks range between 0.5-1.0 arem/hr.
o Waste Gas Building
- This - building- contains . two deactivated waste gas tanks and is nonradio-active.
o- Waste Gas Tunnel ,
J
' The tunnel runs. east to west from the Reactor Building along-side the south
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wall of the Waste Gas. Building. The tunnel steps down as it approaches;the
- Waste Gas Building and becomes too congested and small for access along its .
whole length. AccessLis via a. steel cover southeast of the Waste Gas g_ Building.
Inert Cas Buildins
, .o The south end of this building contains a 500 -cubic foot vacuum tank, a 200
~
cubic foot vapor trap, and a 500 cubic foot hold-up tank. The north room contains'three inert gas. compressors. Both rooms are nonradioactive.
o' NaK Room The room houses the NaK equipment (used in conjunction with the sodium cold trap) which has been disconnected. The sodium drumming facility is 'also -
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- located in this room. Radiation surveys indicate only trace amounts of-radioactive material present in equ{pment and structures in this room.
o' Cold-Trap' Room
- This room contains sodium piping needed formerly for sodium drumming, .and
\, the piping and valves to and from the primary sodium tunnel. Some of the latter has been cut'and capped. Others have had ' the- valves closed and the
- . - handwheels disconnected. Some misc _ellaneous radioactive materials are
'being stored in the' room.
- i. Not shown in Figure l'is a second story above the Cold Trap Room, Nak Room, and part of the Inert -Gas . Building. This second story contains 'the hand-wheels to the sodium valves' at the ' north end of the room (some
' disconnected) and the electrical feeds for sodium heating.
s
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. 3-'
, ~
2 4
'o ' ~ Vent Buildina.
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This building has' been ' emptied of a111 equipment and the fence -has been modified toLbe continuous past the east doors of the building.
o Primary Sodium Tunnel' This tunnel is steel-lined and runs fram-the northwest corner of the Reactor Building to the Cold' Trap Room. The piping in this_ tunnel has been-
. drained and capped at the; Reactor' Building, and either capped or isolated
- with closed disconnect valves in the Cold Trap Room. Access to this tunnel is via a manhole near the transfer corridor.
o' Fission Product Detector' Building This is a small building, partly below ground level, to the. east of the LL Reactor Building._ It contains some slightly radioactive piping.
o Sodium Piping Galleries'
'There~are'two bAlow ground' piping galleries that were used to house (secondary sodium piping.
'The west' gallery consists of two chambers (i.e., north.and south chambers) which hold the __ secondary sodium lines that supplied: the No.- 3 steam generator. The-sodium lines have been capped where they exit and enter the
, Reactor: Building.
- The ground level entry to the north chamber was sealed off as part of the decommissioning program. Entry is now made via a short 30" diameter tunnel
~
which runs between the biological shield wall space and the north chamber.
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' Access to ~ the south chamber islvia's steel door just 'above ground level at the north wall of the Steam Generator building.
The east gallery consists of three separate chambers and contains the secondary; sodium pipe . lines that supplied the Nos. 1 and 2 steam generators.
.These lines.have'been capped as in the. west gallery.'
s
. Access to the' three ~ chambers ;is by means of steel doors just above ground level outside the' southeast quadrant of the Reactor Building.
Jo Biological Shield Wall Area
' _ This ~is approximately a three foot wide annulus that surrounds the building below floor level to about three feet below the concrete pedestal on which the' steel Resctor Building stands. Various service piping systems'are
. located in the annulus.- It 'is entered via a bolted-in-place cover at the west asinuth outside of the containment shell. An access ladder has been-le f t in place. In addition, at 'about 30*; north of -the entrance, at just below floor level, there is an access port to the northwest secondary sodium pipe. gallery chamber. .
I t
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+ . ,
- c. -.
p The annulus has four floor drains that drain into a collection tank and l' '
- sump pump system located'in the basement of the Stema Generator Building.
. In addition, there is'a moisture detector that alarms at the manned control i station. -The water drained into the. tank is nonradioactive.
-o Fuel Transfer Corridor ,
This is a covered way covering the tracks of the former fuel handling cask car. The end adjacent:to the Reactor Building was. modified after 1966 to provide's covered access to the Reactor Building air lock. The area is free of contamination.-
,4 o ; Health Physics Building This' building has been removed.. Only the foundation slab remains.- There are potentially radioactive drains'and lines-to-the hot' sump,in the FARB which have been permanently plugged and marked. Due to some problems with E ; rain water in-leakage via these-drains and.where they penetrate the FARB, 1 'the entire area between the foundation slab and the FARB has been covered l by a concrete slab. Since this has been done, there has been no consequential inleakage. -Radiation levels above the slab are in the same
[ . range as those of natural concrete.
o Primary System Cover Gas The' primary system is defined as the reactor vessel and all connecting volumes.' These include the three primary loops, the machinery done, and-
-the primary sodium service, and secondary sodium systems 'out to the welded -
l fittings.' The primary system is connected to reserve and backup supplies
!! of carbon dioxide to passivate the residual sodium and is kept at approximately two inches water pressure with 'a relief valve set for approximately 5 psig. The relief valve is checked annually for proper h ' operation.
, The cover gas is' instrumented to alarm in the manned control station-at low.
p~ (1/2-in ' water gauge) and high (2 psig increasing pressure) pressure.
Primary cover gas alarm tests are performed every six months.
- o. Liquid Waste Discharge System All potentially contaminated drains and sumps collect in the hot sump in the Fuel and Repair Building. The liquid waste collected in the hot sump
~
is discharged to the liquid waste tanks, (ak 7, 8, 9, 15). Liquid quantities in these tanks are monitored and recorded. If there is a need to discharge the liquid from the tanks, the water will be processed via a portable liquid radwaste processing system such as is typically used at many power reactor facilities until it is acceptable for discharge in accordance with the Technical Specifications.
g i* '
- 0 Liquid waste collected in non-contaminated . sump systems are'not part of the Liquid Waste Discharge System. .Non-contaminated sumps collect underground
- water or rain water intruding in non-contaminated areas. These sumpt 4
Edischarge ~ to the plant drain system which drains to Lake Erie.
o Other "The remaining Fermi 1 buildings (e.g., the -steam generator, control, and office buildings) were not exposed to the radioactivity resulting from the.
operation of Fermi 1. Due to this , they have been used ' for various ,
a
- activities affiliated with~the operation of the oil peaker unit (now
^ decommissioned) and Fermi 2.
' 3.0 ADMINISTRATION.
The Detroit Edison Company has the responsibility for maintaining a continuing administrative and surveillance program in compliance with current Nuclear Regulatory Commission requirements to ensure that the health and safety of>the public and. employees are not threatened or injured.
The Vice President, Nuclear Operations, who reports to the President has overall responsibility for the Enrico Fermi Unit i reactor facility.
Reporting 'to the Vice President, Nuclear Operations, is the Manager and the
- Assistant Manager, Nuclear Operations.
, Responsibility for the decommissioned Enrico Fermi Unit I reactor facility is delegated through the line' organization of the Vice President, Nuclear
. Operations,.'down through the Manager, Nuclear Operations', to a qualified custodian selected from the -staff of the adjacent Fermi 2 Atomic Power Plant. The Custodian is assisted in his duties by Custodial Delegates and Custodial Agents.
~ In addition, the facility administrative. and surveillance program is-audited by means of a Review committee which will also review and approve all matters of safety associated with.any maintenance activities in'the facility. .
! Written procedures delineate the qualification, selection and responsibilities of the Custodian, Custodial Delegates and Ag'ents, and members of the Review-Committee.
4.0 ACCESS CONTROL t
The area encompassed by physical barriers and to which access is controlled is th'e Protected Area. The Protected Area, is enclosed by either a chain link fence or building walls which provide equivalent degree of resistance-
-to penetration. The fence. is topped by three or more strands of barbed
-wire ~or brackets angled outward with an overall height of no less than seven feet. Normal entry to 'the Protected Area is through a normally locked gate in the fence adjacent to the Sodium Building. Other doors in walls' which~ act a part of the Protected Area boundary are locked or
-permanently sealed.
- ( , ~
l l
. Access to the ' Protected ' Area is controlled, limited .and recorded. _The i access key;is in_the manned control statien. A second key is' held in safe l keeping- by.'the Custodian for use only in extenuating circumstances.
Writteniprocedures delineate the requirements associated with entry into the- Protected Area and specific areas within the Protected Area to prevent
' unauthorized entries and to - protect the safety -and -health of authorized personnel.-
5'.0_. MONITORING AND ALARMS' Monitoring- detectors for water. intrusion are located in three areas: (1) the Fuel and Repair, Building basement hot sump, (2) the' Lower reactor Building overflow tank pit, and (3)- the Biological _ Shield Wall Area.
tAccumulation of water'in these areas activates an. alarm in the mannM control station.
The primary system cover gas pressure i's also monitored with high and low alarms. The monitors and the alarm circuitry are periodically checked and
' ~
. -calibrated in accordance with the Technical Specifications and written procedures._ -
6.0L SURVEYS, INSPECTIONS, AND' TESTING Two types 'of surveys _ are identified; environmental and radiological, in
' addition ' to periodic facility inspections and instrumentation testing.
For the environmental surveys, a number of stations have been established where it is estimated that maximum concentrations of: radioactive material di,scharged from the facility' may ' occur. Two different regimes of sampling and' analysis are utilized. A summary of these regimes is given in Table 1.
- 1. Regime I is followed if activity is released.
- 2. Regime II is followed if no activity has been released during the-previous 90 days.
Periodic Radiation _ surveys are performed to check for the presence of gamma radiation'and transferrable contamination at the frequency specified in the .i
. Technical Specifications. _ Gamma radiation measurements using portable survey instruments and contamination checks using smears are made of the following areas:
Reactor Building - Operating floor, doors and seals around machinery dome, breather pipe', sump pump serving Reactor Building annulus.
Fuel and Repair B'uilding - Pool area, operating floor access points to
. contamination areas, Steam cleaning Room access plug.
~
Environmental and radiological surveys are performed by or under supervision of qualified personnel having parallel duties and responsibilities at Fermi 2.
m L
A monthly visual . inspection of the Protected Area is performed by Custodial
~
~
- ' Agents. The inspection consists of a visual inspection ~ of the fence, gates and all; exterior doors ~ at . the . Protected Area, a' check and recording of the level of liquid in the liquid water tanks, a check on the ' condition of the
.strippable paint .on ,the decay and cut-up pools in the Fuel and Repair Building, and ' verifications of f the operation of- the susp pumps which serve the Protected Area. .All abnormal conditions observed are reported to the.
Fermi 2 Nuclear . Shift Supervisor so that. corrective' measures may be taken.
The Custodian is also notified of all abnormal conditions. immediately, and -
of theJcorrective action taken.
Testing'and calibration of the~ water intrusion monitors, and testing the primary cover' gas pressure alarus, is performed every six months. Testing of the carbon dioxide pressure relief valve is performed snnually. all testing :is ' performed in accordance with written and approved procedures.
7.0 5 PROCEDURES Procedures ensure that the requirements of the Technical Specifications are carried out in a proper and timely'manne~r. They also serve as training and reference units for future Custodians, Custodial Delegates and Custodial
' Agents. Administrative -procedures include Custodial qualifications, responsibilities and authority, Procedure Manual control, Custodial .
Delegate and Custodial Agent s' election and. function, reporting procedures, ,
. Review Committee-functions and financial accounting procedures. In 7 addition, .- th'ere are - appropriate procedures for' details of inspections,-
surveillances' and operation.
L 1 .
se 4
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TABLE 1 .!
Environmental Survey Regimes Number of Stations Regime
- Sample Media Indicator Background I II Water-4: South Lagoon' 1 0. G26b G26b River Water-. 1. 1 G1b C26b Lake Water 1 0 Gib G26b Raw City Water
- 0 -3 G4b G26b Sediment South Lagoon Sediment 1 0 G26g G26g River Sediment 1 1 G26g G26g Symbols:
G -' Grab Sample Frequency of Sampling:
1 - one week-interval 4_ . ~ four week interval 26 Lt wenty-six week interval Type of Analysis:
b - be t a -
g gamma
-Example : Gib - Sample is collected at one week intervals and analyzed for beta radioactivity
Detroit.
Monroe
, Fermi Plant
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- 2 2 2 2 2 2 1/ 2 2 2 a 2 1 2 21 I[ { f /f{ f f f f f f f f ff 4
9 11 / / 11 f f 1 1 ff
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S 8 i
q _____a , .
s y _ _ _ _ HEALTH PHYSICS l'ULL AND RLPAlk I l U s BUILDING g BUILDING l*
N (NOTEA) I s\ L____________J 3 \
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11 COLD I
l S0DIUM STORAGE TRAP :E BUILDING ROOM ::
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BUILDING 3Ei: -
- :6:
s 0FFICE BUILDING CONTROL BUILDING STEAM GENERATOR BUILDING LEGEND: FENCE ///////////- NOTE A: BUILDING HAS BEEN DISMANTLED ONLY SLAB REMAINS l
FIGURE 1 I FACILITY PLAN l u