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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
_ _ _ _ _ _ _ _ _ _ __ ____________
. Douglas R. Gipson Senior Vive President, Nuclear Generation Fermi 2 L 6400 North Dixie llwy., Newport, Michigan 48166 l Tel: 313.586.5201 Frx 313.586.4172 Detroit Edison July 17,1998 L NRC-98-0044 -
L U. S. Nuclear Regulatory Commission L a ~ Attention: Document Control Desk
- Washington, D C 20555-0001 ,
References:
- 1) Enrico Fermi Atomic Power Plant, Unit No. I NRC Docket No,50-16 j NRC License No. DPR-9 j
- 2) Detroit Edison Letter, NRC-98-0023,
" Proposed License Amendment to Allow Possession ofContaminated Apparatus j L and Sources", dated January 28,1998 l
Subject:
Proposed License Amendment -
- l. To A' low Possession of a Nominal Amount of Specnd Nuclear Material L Pursuant to'10 CFR 50.90, Detroit Edison hereby proposes to amend Possession -
Only License DPR-9 for the Fermi I plant by modifying Pan 2.B of the License.
L. This application proposes to allow Detroit Edison to possess special nuclear material -
(SNM)in a quantity totaling no more than 15 grams ofuranium-235, uranium-233 or [
plutonium, or any combination thereof, with plutonium activity totaling no more than /
l 2 curies.
l-
- The reason for this change is to allow Detroit Edison to possess nominal quantities of L special nuclear material that may remain in plant systems or be associated with l; radioactive apparatus or equipment. The 15 gram and 2 curie limit specified is below /
the criteria requiring emergency planning, criticality monitoring, or material status d)l l- ! repons per 10 CFR 70 and 10 CFR 74.
, The description and evaluation of the changes are included in Enclosure 1 to this letter, i
Detroit Edison requests prompt approval of this request and asks that this amendment
,3 G4'7 be approved with an implementation time period of"within 60 days." This will allow approval of procedure changes needed to implement the amendment.
!- . 9907240133 980717 [ ' '
i PDR ADOCK 05000016 y l P PDR i- A DTE Energy Company L '*'- _ >
USNRC
. NRC-98-0044
.Page 2 Detroit Edison has evaluated the proposed change against the criteria of 10 CFR 50.92 and determined that No Significant Hazards Consideration is involved. The Fermi 1 Review Committee has reviewed and approved the proposed amendment. In accordance with 10 CFR 50.91, Detroit Edison is providing a copy of this letter to the State of Michigan.
If there are any questions, please contact Lynne Goodman, Director Fermi 1 at 734-586-1205.
Sincerely, ,
4 Enclosure cc: Regional Administrator, NRC Region III S.W. Brown G.A. Harris P. Lee, NRC Region III Director, Office of NMSS,NRC I.
7 SHARON K. 8JCKLEY
-)
% Pubuc Monroe County
% c==wm,apo.s.g n,,MI m -/7-M-i l
USNRC NRC-98-0044
.Page 3 I, DOUGLAS R. GIPSON, do hereby aflirm that the foregoing statements are based on facts and circumstances which are true and accurate to the best of my knowledge
'and belief.
1 M
DOUGLAS RIGIPSON Senior Vice President On this day of- 9 .1998 before me personally I L'
, appeared Douglas R. Gipson, being first duly swom and says that he executed the foregoing as his free act and deed -
N f '
Notary Public l KAREN M. RES "d$yE s erset N l
l
___-__________-_-__a
Enclosure 1 NRC-98-0044 Page1 .
ENCLOSURE 1 DESCRIPTION AND EVALUATION OF PROPOSED LICENSE AMENDMENT TO ALLOW POSSESSION OF A NOMINAL AMOUNT OF SPECIAL NUCLEAR MATERIAL Enrico Fermi Atomic Power Plant, Unit 1 NRC Docket No. 50-16 NRC License No. DPR-9 l
l
Enclosure 1 -
NRC-98-0044 Page 2 4
' INTRODUCTION This proposed amendment requests that Detroit Edison be allowed to possess special nuclear material in a quantity totaling no more than 15 grams of U-235, U-233, or plutonium, or any combination thereof and with plutonium activity totaling no more than 2 curies.
The reason for this request is to allow Detroit Edison to possess nominal quantities of special nuclear material that remain in plant systems from operation of the reactor or are associated with
. radioactive apparatus or equipment. During the original decommissioning of the Fermi 1 V facility, all fuel and blanket materials were removed from the site. ' After the blanket material was removed, the special nuclear material sections of the license _were deleted. However, it is now believed that trace quantities of special nuclear material may be contained in plant systems. The literal words of the license do not cover possession of special nuclear material remaining from L plant operation, since only possession of the reactor and byproduct material are addressed. The '
10 CFR 30 definition of byproduct material excludes special nuclear material.
One' composite smear sample from the liquid waste sump, analyzed for 10 CFR 61 l characterization purposes in 1995 by an outside laboratory, did show a small amount of Pu-239/240. The result was 1.27 E-5 Ci. During review of the recent amendment request
. submitted in Reference 2, the results of this 1995 smear analysis were compared to the wording .
'in the license. Personnel recognized that the literal wording in the license does not specifically allow possession of special nuclear material contained in plant contamination. Review of the licensing history concluded that the provisions for possessing special nuclear material were removed from the license after the reactor blanket material was shipped offsite. Since the fuel had earlier been removed, it was concluded at that time (c.1975) that all special nuclear material .
_was gone. ' Any small amounts of material remaining in system contamination were not ,
. addressed, nor was any special nuclear material identified in any sample results reported in the
)
[ Retirement Reports. !
I L . Fifty additional smears from the area were taken in January 1998 and counted on a Tennelec ~
B : Automated Counter. Alpha radiation was not detected. if a significant quantity of plutonium
- was present, alpha or appreciable beta activity would have been detected. Additional smears .
.were taken February 11,1998, until detectable activity was measured. While no alpha activity ;
was detected on the smears using the Tennelec Automated Counter, smears with detectable j h radioactive contamination are considered more likely to contain plutonium than smears with ;
L lesser contamination. Two smear samples with measurable beta activity were sent offsite for j additional, more sensitive analysis. The results were received in May 1998. The composite of the smears was analyzed to have 1.04 E-2 Ci of Pu-239/240 and 2.16 E-3 pCi of Pu-238.
l
. . 1
. J Enclosure 1 NRC-98-0044 Page 3 - -
The 1998 smear results were higher in Pu-239/240 and Pu-238 content than the 1995 analysis.
Previous analyses of hot sump water and waste tank water did not identify plutonium. A conclusion can be reached that the remaining plutonium is not evenly spread throughout the 3 system. Very localized deposits may be present in the liquid waste system. Both the 1995 and
.1998 composite smears on which the plutonium was detected had been taken from the surface of a sump pump that had previously been removed from its installed location in the sump and-placed on the grating.
To estimate the amount of plutonium in the system, the ratio of the amount of plutonium in the 1998 smears to amount of Co-60 was multiplied by the licensing basis estimate of Co-60 in the l
j waste system, which was 6.0 E+3 pCi. This estimate is conservative since the 1998 plutonium content on the smears was higher than the previous analyses and the licensing basis Co-60 estimate for the waste system was performed in 1986. The total waste system inventory of plutonium is estimated to be less than 1 gram. Note that the amount in the waste system is less than the limit of error allowed in current regulations in 10 CFR 70.51(e)(5) for special nuclear material accountability. ,
l
. Whether plutonium is also deposited elsewhere inside plant systems, such as inside the primary system is not known. The internals of the reactor vessel are not currently accessible to obtain samples. A sample from a drum of primary sodium from Fermi 1 was analyzed at Argonne National Laboratory-West in 1997. The Pu-239 concentration was less than the minimum detectable activity (<2.3 E-4 Ci/g).
Activities at the plant during operation and decommissioning could conceivably have led to small quan@ce of special nuclear material remaining in primary system or waste system contamina%i. These divities include the cutting of fuel and blanket subassemblies prior to shipping and the 1966 damage to two subassemblies. Therefore, Detroit Edison believes this amendment is warranted.
- Since it is possible that additional special nuclear material could be detected at a later date when additional systems are opened or samples taken, Detroit Edison is proposing that the license also accommodate additional special nuclear material if found in the future. If the threshold for
, special nuclear material oflow strategic significance is exceeded based on additional material identified, the regulatory requirements for the amount of special nuclear material identified will l apply at that time.
- Regulatory Guide 1.86, " Termination of Operating Licenses for Nuclear Reactors", does address that a licensee having a possession-only license needs to maintain a special nuclear material license until the fuel, radioactive components, and sources are removed from the facility.
Radioactive components remain at Fermi 1 during the current SAFSTOR status.
To allow possession of trace amounts of special nuclear material, Detroit Edison proposes to add
- subpart 4 to Part 2.B of the Fermi 1 license, reading as follows:
l l
1 Cz________________ _ __ _ . _
j
4 Enclosure 1
' NRC-98-0044 '
Page 4 - *
(4) Pursuant to the Act and 10 CFR Part 70," Domestic Licensing of Special Nuclear Material" to receive, acquire, possess, use and transfer, but not separate, special nuclear material in a quantity not to exceed 15 grams of U-235, U-233, or plutonium, or any combination thereof and not to exceed plutonium activity of 2 curies. If special nuclear
- material in quantities exceeding 15 grams or more than 2 curies ofplutonium are identified in plant contamination in the future, this license permits possession and transfer of the special nuclear material and the additional applicable requirements of 10 CFR Part 70, Part 73, and Part 74 will apply for the amount possessed.
EVALUATION The proposed amendment to allow Detroit Edison to possess a small amount of special nuclear j material limits the amount to not exceed 15 grams of U-235, U-233, or plutonium, or any I combination thereof and the plutonium activity not to exceed 2 curies. This amendment will I allow Detroit Edison to possess trace amounts of special nuclear material that remain in plant !
systems, recognizing that all fuel and blanket assemblies were removed from the site. The majority of analyses performed on samples from Fermi I systems have not identified any special ,
nuclear material, including the analyses at the end of the original decommissioning or when preparing information for the SAFSTOR license in the 1980s. As discussed earlier, two composite smear samples have been analyzed and contain a very small amount ofplutonium.
Also, it is possible that contaminated apparatus, tools, hardware, or equipment may contain incidental amounts of special nuclear material. Therefore, the proposed amendment requests
' Detroit Edison be allowed to receive, acquire, possess, use and transfer, but not separate, up to 15 grams of U-235, U-233, or plutonium, with the plutonium activity not to exceed 2 curies.
The limit was chosen to be very low so the amount of special nuclear material permitted by the license is below the criteria of 10 CFR 70 requiring material status reports, criticality monitoring,
. a formal security plan, an emergency plan or maximum release evaluation. Based on the small amount of special nuclear material this amendment would authorize, the existing radiation protection program will function to protect the health and safety of facility personnel and the public. The additional requirement will be to track and keep records of the quantity of special nuclear material at Fermi 1 and to ensure the licensed limit is not exceeded. This includes records of receipt, inventory (including location), disposal, acquisition, and transfer of special nuclear material. Tracking the amount contained in plant systems will need to be based on l L estimates from current and future analyses. Reporting requirements of 10 CFR 74.11 regarding j l theft or diversion of special nuclear material will also apply. Requirements for transferring !
special nuclear material per 10 CFR 74 will also apply, but special nuclear material control,
' physical inventory, and accounting requirements of 10 CFR 74 and 10 CFR 70 will not apply. ]
The definitions in 10 CFR 70.4 include three categories of special nuclear material based on mass. The 15 grams requested in this letter falls below the criteria for the lowest class defined, !
that of special nuclear material oflow strategic sigmficance. This category applies only to I z - - - --_
4 Enclosure 1 NRC-98-0044 Page 5 .
amounts greater than 15 grams. In addition to being below the amount requiring a security plan or contingency plan per 10 CFR 70, the fixed site requirements for special nuclear material
. physical pro'tection per 10 CFR 73 do not apply to quantities below special nuclear material of low strategic significance. Section 10 CFR 73.55 details requirements for physical protection of
- licensed activities in nuclear power reactors against radiological sabotage. While Fermi 1 is licensed as a power reactor, it does not have a security plan, nor is it licensed to possess reactor fuel.. Detroit Edison is licensed to possess, but not operate the facility. The Commission can authorize a licensee to provide alternate measures. In this case, since Fermi 1 is not licensed to operate or possess fuel, the requirements for physical protection for special nuclear material are more appropriate than the 10 CFR 73.55 power reactor requirements. The amount of special nuclear material requested by this license amendment is below the criteria of 10 CFR 70 and 10 CFR 73.67 for requiring protection at fixed sites, so the NRC has already &termined physical protection is not needed for such a small amount of special nuclear material at a fixed site. The Fermi 1 Technical Specifications do specify requirements for site security and access control to
- the Fermi 1 Protected Area.
An estimation of the impact of the radionuclides identified on the smears on the liquid waste accident analysis has been performed. The draft Fermi 1 Safety Analysis Report is being updated based on the evaluation.
Based on the small amount of special nuclear material being requested to be licensed at Fermi 1, that the amount is less than the definition for special nuclear material oflow strategic significance, that the material will be contained in plant contamination or in incidental amounts on contaminated apparatus, tools, hardware, or equipment, this request does not introduce any new challenges to safety at the Fermi I facility. Also, separation of special nuclear material is not being requested by the license amendment,~
If additional special nuclear material is identified in plant contamination in the future, the proposed amendment will require the established applicable regulatory requirements of 10 CFR Part 70, Part 73, and Part 74 to apply if 15 grams of special nuclear material or 2 curies of plutonium is exceeded. The license as proposed will only permit possession and transfer of
' ~
more than 15 grams of special nuclear material or 2 curies of plutonium ifit is identified in plant contamination and so already at Fermi 1. The proposed license wording allows transfer to enable future decontamination and disposal. Since the already established applicable regulatory requirements for the amount of special nuclear material will apply if more than 15 grams of material or 2 curies of plutonium is identified in the future, this proposed provision will ensure appropriate actions are taken for safe possession of the material.
SIGNIFICANT HAZARDS CONSIDERATION i
In accordance with 10 CFR 50.92, Detroit Edison has made a determination that the proposed amendment involves no significant hazards consideration. To make this determination, Detroit L
E _ _ - _ - _ _ - - -
'- Enclosure 1 NRC-98-0044 Page 6 .
i Edison must estabh6 thrt conduct of acf vities in accordance with the proposed amendment
, would not: (1) invoh; a significant increase in the probability or consequences of an accident previously evaluated; or (2) create the p ossibility of a new or different kind of accident from any accident previously evaluated; or (3) iNolve a significant reduction in a margin of safety.
- 1. The proposed amendment does not involve a significant increase in the probability or consequences of an accident. Possessing trace amounts of special nuclear material cannot affect the probability of the analyzed sodium or liquid waste accidents. The ability to possess such material does not in itself change any methods of handling liquid waste or sodium. Possession of special nuclear material could potentially increase the consequences of an accident ifit was in use or in the vicinity if an accident occurs. However, the increase in consequences would not be significant due to the limitations on radioactivity content of such special nuclear material. The special nuclear material limit is below that requiring an emergency plan or maximum dose evaluation per 10 CFR 70.22(i). Since the quantity is below that requiring an offsite emergency plan or evaluation, even if all the special nuclear material allowed to be possessed by the proposed amendment were released during a postulated accident, the consequences would not be significantly increased. If the !
provision allowing for possession of more than 15 grams of special nuclear material or ,
2 curies of plutonium is identified in plant contamination in the future were to be used, the I requirements of 10 CFR 70.22(i) would need to be assessed and a dose evaluation performed or an emergency plan submitted if required to ensure the analyzed accident is L appropriately addressed and mitigated. Any such special nuclear material would be l contained in remaining plant contamination since fuel and blanket material were shipped offsite during 1973 - 1975. Therefore, this amendment does not involve a significant l increase in the probability or consequences of an accident.
- 2. The proposed amendment does not create the possibility of a new or different type of j accident from any previously evaluated. Allowing possession of small amounts of special ;
nuclear material does not change methods of monitoring the facility or operation or smveillance of any systems at Fermi 1. The amount requested is below that requiring L criticality monitoring per 10 CFR 70.24 and separation of the'special nuclear material will L . not be permitted. Thus, there is no identified physical mechanism for creating an accident based on the existance of such material in the quantities specified. If the provision ,
allowing for possession of more than 15 grams of special nuclear material or 2 curies of l plutonium ifidentified in plant contamination in the future were to be invoked, applicable provisions to ensure public safety per 10 CFR Part 70, Part 73, and Part 74 will apply. For these reasons, allowing Detroit Edison to possess very limited amounts of special nuclear .
material at Fermi 1 will not create the possibility of a new or different type of accident. I w
m-----a -.--- - - - _ - . . - - - . - - -
,1
' ~
Enclosure 1 NRC-98-0044 Page 7 .
- 3. The proposed amendment does not involve a significant reduction in the margin of safety at Fermi 1. No changes to any systems, or the status of any systems or structures, are created by this amendment. Being able to have a very limited amount of special nuclear material at Fermi 1 will not significantly reduce the margin of safety because a 10 CFR Part 20
. program is already in place and the amount of special nuclear material is being limited
.below criteria requiring an emergency plan, security plan, special material control program
. or criticality monitoring. If more than 15 grams of special nuclear material or 2 curies of plutonium is identified in plant contamination in the future, the proposed license amendment will require the applicable portions of 10 CFR Part 70, Part 73, and Part 74 to apply for the amount identified. For these reasons, this amendment will not significantly reduce the margin of safety at Fermi 1.
ENVIRONMENTAL IMPACT
' Detroit Edison has reviewed the proposed amendment against the criteria of 10 CFR 51.22 for environmental considerations. The proposed changes do not involve a significant hazards consideration, nor significantly change the types or increase the amounts of effluents that may be released offsite, nor significantly increase individual or cumulative occupational radiation
, exposures, due to the very limited amount of special nuclear material being licensed. Based on i the foregoing, Detroit Edison concludes that the proposed amendment meets the criteria given in 10 CFR .51.22 (c) (9) for a categorical exclusion from the requirements for an Environmental
! Impact Statement. Also, the criteria of 10 CFR 51.22(c)(14) are met since the quantity of special
- nuclear material being added to the license is incidental because it is very small and associated L with contaminated systems at the facility or contaminated apparatus, tools, hardware or equipment.
CONCLUSION i-Based on the evaluations above: (1) there is reasonable assurance that the health and safety of the public will not be endangered by conduct of activities in the proposed manner; (2) such activities will be conducted in compliance with the Commission's regulations; and (3) the proposed amendment will not be inimical to the common defense and security or the health and i safety of the public. !
l
- Detroit Edison requests that the proposed license amendment be effective within 60 days of i p . approval by the Commission.
I i
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