Letter Sequence Request |
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Results
Other: AECM-85-0289, Forwards Revised Proposed Tech Spec Change Concerning Spent Fuel Pool & Upper Containment Pool Storage Capacity After Installation of High Density Spent Fuel Racks,Per 850506 Submittal, AECM-85-0297, Forwards Correction to Table 1 of 850815 Final Response to NRC Question Re Dynamic Analysis of High Density Spent Fuel Racks Proposed for Installation at Facility, AECM-85-0352, Forwards Clarification of Use of Stress Criteria for High Density Spent Fuel Racks,In Response to NRC Request.Stress Criteria Differences Between OT Position Paper & NUREG-0800 Amount to Same Limits for Rack Modules, AECM-86-0077, Forwards Revised Spent Fuel Loading Pattern Developed to Maintain Dose Rate Contribution from Spent Fuel in Auxiliary Bldg Spent Fuel Pool Area Below 2.5 Mrems/H for Routinely Accessible Areas, AECM-86-0179, Forwards Revised Tech Spec Page 5-6 Inadvertently Omitted from 860605 Submittal Re High Density Spent Fuel Racks, AECM-86-0229, Forwards Responses to NRC Concerns Re Spent Fuel Decay Heat Capability & Associated Operating Procedures,Per 860716 Telcon.Requests That OL Amend for High Density Racks Be Granted on 860818, ML20117C275, ML20117C283, ML20205D440, ML20205T067
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MONTHYEARML20117C2831985-05-0606 May 1985 Licensing Rept,High-Density Spent Fuel Racks Project stage: Other AECM-85-0143, Forwards Application for Amend to License NPF-29,changing Tech Specs to Allow Replacement of low-density Aluminum Spent Fuel Racks w/high-density Spent Fuel Racks. Licensing Rept,High-Density Spent Fuel Racks, Encl.Fee Paid1985-05-0606 May 1985 Forwards Application for Amend to License NPF-29,changing Tech Specs to Allow Replacement of low-density Aluminum Spent Fuel Racks w/high-density Spent Fuel Racks. Licensing Rept,High-Density Spent Fuel Racks, Encl.Fee Paid Project stage: Request ML20117C2611985-05-0606 May 1985 Application for Amend to License NPF-29,changing Tech Specs to Allow Replacement of Current low-density Aluminum Spent Fuel Racks w/high-density Spent Fuel Racks to Provide Increased Storage Capacity Project stage: Request ML20117C2751985-05-0606 May 1985 Proposed Tech Specs Allowing Replacement of Current low-density Aluminum Spent Fuel Racks w/high-density Spent Fuel Racks to Provide Increased Storage Capacity Project stage: Other ML20129F9581985-07-0505 July 1985 Forwards Request for Addl Info Re High Density Spent Fuel Racks in Upper Containment Pool & in Spent Fuel Storage Pool.Response Due by 850715 Project stage: RAI ML20133A1781985-07-26026 July 1985 Forwards Request for Addl Info Re Application to Amend License NPF-29,allowing Installation of High Density Spent Fuel Racks in Upper Containment Pool & Spent Fuel Storage Pool.Info Requested by 850815 Project stage: RAI AECM-85-0229, Responds to 850705 Request for Addl Info Re Structural Analyses Presented in 850506 Application for Amend to License NPF-29,allowing Installation of High Density Spent Fuel Racks.Direct Stress Below Liner Matl Ultimate Stress1985-07-29029 July 1985 Responds to 850705 Request for Addl Info Re Structural Analyses Presented in 850506 Application for Amend to License NPF-29,allowing Installation of High Density Spent Fuel Racks.Direct Stress Below Liner Matl Ultimate Stress Project stage: Request ML20136H1801985-08-0909 August 1985 Forwards Request for Addl Info Re 850506 Request for Amend to License NPF-29,allowing Installation of High Density Spent Fuel Racks in Upper Containment Pool & in Spent Storage Pool.Info Requested by 850826 Project stage: RAI AECM-85-0252, Responds to NRC 850705 Request for Addl Info Re Structural Analyses Presented in Application for Amend to License NPF-29,authorizing Installation of High Density Spent Fuel Racks.Info Re Numerical Solution of Dynamic Analyses Encl1985-08-15015 August 1985 Responds to NRC 850705 Request for Addl Info Re Structural Analyses Presented in Application for Amend to License NPF-29,authorizing Installation of High Density Spent Fuel Racks.Info Re Numerical Solution of Dynamic Analyses Encl Project stage: Request AECM-85-0272, Forwards Response to NRC 850726 Request for Addl Info Re Amend to License NPF-29,allowing Installation of High Density Spent Fuel Racks.Tech Spec Section 4.5 Changed to Conform to Ref Design Used in Analysis1985-08-30030 August 1985 Forwards Response to NRC 850726 Request for Addl Info Re Amend to License NPF-29,allowing Installation of High Density Spent Fuel Racks.Tech Spec Section 4.5 Changed to Conform to Ref Design Used in Analysis Project stage: Request AECM-85-0297, Forwards Correction to Table 1 of 850815 Final Response to NRC Question Re Dynamic Analysis of High Density Spent Fuel Racks Proposed for Installation at Facility1985-09-11011 September 1985 Forwards Correction to Table 1 of 850815 Final Response to NRC Question Re Dynamic Analysis of High Density Spent Fuel Racks Proposed for Installation at Facility Project stage: Other AECM-85-0289, Forwards Revised Proposed Tech Spec Change Concerning Spent Fuel Pool & Upper Containment Pool Storage Capacity After Installation of High Density Spent Fuel Racks,Per 850506 Submittal1985-09-12012 September 1985 Forwards Revised Proposed Tech Spec Change Concerning Spent Fuel Pool & Upper Containment Pool Storage Capacity After Installation of High Density Spent Fuel Racks,Per 850506 Submittal Project stage: Other AECM-85-0352, Forwards Clarification of Use of Stress Criteria for High Density Spent Fuel Racks,In Response to NRC Request.Stress Criteria Differences Between OT Position Paper & NUREG-0800 Amount to Same Limits for Rack Modules1985-11-0101 November 1985 Forwards Clarification of Use of Stress Criteria for High Density Spent Fuel Racks,In Response to NRC Request.Stress Criteria Differences Between OT Position Paper & NUREG-0800 Amount to Same Limits for Rack Modules Project stage: Other AECM-85-0410, Forwards Response to NRC Request to Determine & Submit Occupational Exposures Associated W/Operation W/High Density Spent Fuel Racks,Per 850506 Application for Amend to License NPF-29,allowing Installation of Racks1985-12-18018 December 1985 Forwards Response to NRC Request to Determine & Submit Occupational Exposures Associated W/Operation W/High Density Spent Fuel Racks,Per 850506 Application for Amend to License NPF-29,allowing Installation of Racks Project stage: Request AECM-86-0077, Forwards Revised Spent Fuel Loading Pattern Developed to Maintain Dose Rate Contribution from Spent Fuel in Auxiliary Bldg Spent Fuel Pool Area Below 2.5 Mrems/H for Routinely Accessible Areas1986-03-14014 March 1986 Forwards Revised Spent Fuel Loading Pattern Developed to Maintain Dose Rate Contribution from Spent Fuel in Auxiliary Bldg Spent Fuel Pool Area Below 2.5 Mrems/H for Routinely Accessible Areas Project stage: Other AECM-86-0011, Responds to 850809 Request for Addl Info Re 850506 Application for Amend to License NPF-29,allowing for Installation of High Density Spent Fuel Racks1986-03-15015 March 1986 Responds to 850809 Request for Addl Info Re 850506 Application for Amend to License NPF-29,allowing for Installation of High Density Spent Fuel Racks Project stage: Request AECM-86-0176, Application for Amend to License NPF-29,changing Tech Specs 3/4.7.9.1 & 5.6.3 Re Installation of High Density Spent Fuel Racks,In Response to NRC Concerns from Review of Util .Affirmation & Justification for Change Encl1986-06-0505 June 1986 Application for Amend to License NPF-29,changing Tech Specs 3/4.7.9.1 & 5.6.3 Re Installation of High Density Spent Fuel Racks,In Response to NRC Concerns from Review of Util .Affirmation & Justification for Change Encl Project stage: Request ML20205T3631986-06-0505 June 1986 Proposed Changes to Tech Specs 3/4.7.9.1 & 5.6.3 Re Installation of High Density Spent Fuel Racks Project stage: Request ML20205T0671986-06-0909 June 1986 Revised Tech Spec Page 5-6 Re High Density Spent Fuel Racks Project stage: Other AECM-86-0179, Forwards Revised Tech Spec Page 5-6 Inadvertently Omitted from 860605 Submittal Re High Density Spent Fuel Racks1986-06-0909 June 1986 Forwards Revised Tech Spec Page 5-6 Inadvertently Omitted from 860605 Submittal Re High Density Spent Fuel Racks Project stage: Other AECM-86-0229, Forwards Responses to NRC Concerns Re Spent Fuel Decay Heat Capability & Associated Operating Procedures,Per 860716 Telcon.Requests That OL Amend for High Density Racks Be Granted on 8608181986-07-25025 July 1986 Forwards Responses to NRC Concerns Re Spent Fuel Decay Heat Capability & Associated Operating Procedures,Per 860716 Telcon.Requests That OL Amend for High Density Racks Be Granted on 860818 Project stage: Other ML20205D4401986-07-28028 July 1986 Notice of Violation from Insp on 860613-0714 Project stage: Other 1985-08-09
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Category:OPERATING LICENSES-APPLIATION TO AMEND-RENEW EXISTING
MONTHYEARML20217F1951999-10-0707 October 1999 Application for Amend to License NPF-29,to Revise Licensing Basis to Credit One of Insights/Conclusions of NUREG-1465, Revised Source Term Insights ML20211E7061999-08-20020 August 1999 Application for Amend to License NPF-29,incorporating Many of Generic Improvements Agreed Upon Between Industry & NRC Since GGNS Conversion to ITS ML20196K0791999-06-29029 June 1999 Suppl to 980720 Application for Amend to License NPF-29, Implementing BWROG Enhanced Option I-A,reactor Stability long-term Solution.Rev to TS 3.4.1 Inadvertently Omitted from Original Application ML20196G6901999-06-23023 June 1999 Application for Amend to License NPF-29,revising TS Associated with Various Esfss Which Need No Longer Be Credited Following Design Basis Fuel Handling Accident ML20206K5241999-05-0606 May 1999 Application for Amend to License NPF-29,changing TSs Required to Support Ggns,Cycle 11 Operation,Including Slmcpr.Portions of Encl Re Addl Info on Calculated Cycle Specific SL MCPR for Plant Cycle 11 Withheld ML20206R9271999-01-12012 January 1999 Application for Amends to Licenses NPF-29 & NPF-47,proposing Required Actions Consistent with NRC Accepted Change to BWR Improved TS NUREG-1433 & NUREG-1434 ML20236T1551998-07-20020 July 1998 Application for Amend to License NPF-29,revising TSs Re BWROG Enhanced Option I-A Reactor Stability Long Term Solution ML20198J3451998-01-0909 January 1998 Revised Application for Amend to License NPF-29,providing Clarifications to Amend & Adding Restriction to Allowed Interval Extensions Re Option B of 10CFR50,app J ML20198N3851997-10-28028 October 1997 Application for Amend to License NPF-29,revising TS to Implement Option B & Ref SE Issued by NRR for Ggns'S App J Exemption as Implementing Document for performance-based Leakage Testing Program ML20210V5461997-09-18018 September 1997 Application for Amend to License NPF-29,reflecting Decrease of Two Recirculation Loop SLMCPR to 1.11 & Single Recirculation Loop SLMCPR Limit to 1.12.Proprietary Info Re SLMCPR for Cycle 10,encl.Proprietary Info Withheld ML20134E1191996-10-22022 October 1996 Application for Amend to License NPF-29,revising TS Figure 3.4.11-1, Minimum Reactor Vessel Metal Temperature Vs Reactor Vessel Pressure, Curves Using Methodology of Reg Guide 1.99,Rev 2, Radiation Embrittlement.. ML20117P4421996-09-19019 September 1996 Application for Amend to License NPF-29,changing Containment Purge Valves W/Resilient Seals on Performance Based Leakage Testing Frequency ML20117G6661996-08-27027 August 1996 Application for Amend to License NPF-29,modifying Tech Specs Surveillance Requirements for Safety/Relief Valves ML20116F0141996-07-31031 July 1996 Rev 1 to Application for Amend to License NPF-29,revising TSs Required to Support Cycle 9,reload 8.Rev 1 to J11-02863SLMCPR, GGNS Cycle 9 Safety Limit MCPR Analysis Encl.Rept Withheld ML20113B7341996-06-20020 June 1996 Application for Amend to License NPF-29,redefining Secondary Containment Boundary to Allow Encl Bldg to Be Inoperable During Upcoming Refueling Outage ML20112E1741996-05-31031 May 1996 Application for Amends to Licenses NPF-29 & NPF-47 Adding Addl Acceptable Required Actions to Tech Spec Limiting Condition for Operation (LCO) 3.9.1, Refueling Equipment Interlocks ML20117F4541996-05-0909 May 1996 Application for Amend to License NPF-29,modifying SRV Surveillance Test for Relief Mode of Operation ML20117D6901996-05-0909 May 1996 Application for Amend to License NPF-29,revising TSs to Support Unit 1,cycle 9 Including Changes to SLMCPR & Ref for Analytical Methods Used to Determine Core Operating Limits ML20111B2631996-05-0808 May 1996 Application for Amend to License NPF-29,placing Containment Purge Valves W/Resilient Seals on Performance Based Leakage Testing Frequency ML20108E3551996-05-0606 May 1996 Application for Amend to License NPF-29,changing Name from Mississippi Power & Light to Entergy Mississippi,Inc ML20107E2521996-04-18018 April 1996 Application for Amend to License NPF-29,prohibiting Performance of 24-h EDG Maint Run While Unit in Either Mode 1/2 RBG-42766, Application for Amends to Licenses NPF-29 & NPF-47,adding Addl Acceptable Method of Fuel Movement,Control Rods Removed or Withdrawn from Defueled Core Cells1996-04-18018 April 1996 Application for Amends to Licenses NPF-29 & NPF-47,adding Addl Acceptable Method of Fuel Movement,Control Rods Removed or Withdrawn from Defueled Core Cells ML20100J8311996-02-22022 February 1996 Application for Amend to License NPF-29,modifying Safety Setpoint to Tolerance Requirements for Safety/Relief Valves ML20097C3491996-02-0101 February 1996 Application for Amend to License NPF-29,revising TS Bases to Include Changes Since 950221 Approval of TS Bases RBG-42193, Rev to Application for Amend to License NPF-29 & Proposed Amend to License NPF-47,revising TS 3/4.6.2.2, Drywell Bypass Leakage1995-11-20020 November 1995 Rev to Application for Amend to License NPF-29 & Proposed Amend to License NPF-47,revising TS 3/4.6.2.2, Drywell Bypass Leakage ML20087B5031995-08-0101 August 1995 Application for Amend to License NPF-29,by Revising TS Assoc W/Various ESF Sys Following Design Fuel Handling Accident ML20086N2071995-07-21021 July 1995 Application for Amend to License NPF-29,proposing to Recapture Approx 2 1/2 Yrs of Low/No Power Operation by Extending 40-yr Operating License Term from 220616 to 241101 ML20078S4891995-02-14014 February 1995 Application for Amend to License NPF-29 Consisting of Changes to TS Requirements 4.4.1.4.a.1 & 4.6.1.4.a.2 ML20078N6481995-02-10010 February 1995 Application for Amend to License NPF-29,consisting of Mod to Proposed Amend to OL (PCOL-93/13),requesting to Perform Drywell Bypass Leakage Rate Surveillance on Performance Based Interval ML20079B4431994-11-0909 November 1994 Application for Amend to License NPF-29,revising TS Associated W/Various ESF Sys Following Design Basis Fuel Handling accident.Mark-up of Current Ts,Proposed TS & mark- Up Improved TS Encl ML20076F9781994-10-12012 October 1994 Application for Amend to License NPF-29,consisting of PCOL-94/01,closing & Deleting License Condition 2.C.(26) for Turbine Disc integrity.Mark-up of Affected OL Page & Proprietary Supporting Info Encl.Proprietary Info Withheld ML20069P4401994-06-17017 June 1994 Proposed Amend to OL (PCOL-94/02),removing License Conditions for EDGs Associated w/NUREG-1216 ML20059H6011994-01-13013 January 1994 Application for Amend to License NPF-29,consisting of Proposed Amend to OL PCOL-93/15,removing 2,324 Spent Fuel Pool Storage Limit & Allowing Full Use of Spent Fuel Storage Spaces ML20059A4801993-10-22022 October 1993 Application for Amend to License NPF-29,modifying Testing Frequencies for Drywell Bypass Test & Airlock Tests ML20059B0131993-10-15015 October 1993 Application for Amend to License NPF-29,converting Current GGNS TS to TS Based Largely on NUREG-1434,Rev 0 ML20056E2861993-08-17017 August 1993 Application for Amend to License NPF-29,proposing Changes to Amend TS Section 3/4.3.7.10, Loose Part Detection Sys by Relocating Loose Part Detection Instrumentation to Administrative Controls ML20056D5321993-08-11011 August 1993 Proposed Change to OL (PCOL-93/09) to License NPF-29, Amending TS Section 3/4.3.7.5 by Relocating Certain Accident Monitoring Instrumentation from TS to Administrative Control,Per NUREG-1434,Rev 0,w/respect to RG 1.97 ML20046D2041993-08-11011 August 1993 Proposed Change to OL (PCOL-93/07) to License NPF-29, Amending TS Section 3/4.3.7.10, Loose Part Detection Sys by Relocating Locating Loose Part Detection Instrumentation from TS to Administrative Controls,Per NUREG-1434,Rev 0 ML20046D1911993-08-11011 August 1993 Proposed Change to OL (PCOL-93/06) to License NPF-29, Revising TS to Support Compliance W/New Requirements of 10CFR20 & 10CFR50.36a ML20056C7131993-07-15015 July 1993 Application for Amend to License NPF-29,proposing Changes to Remove Operability Requirements for auto-test Feature of Load Shedding & Sequencing Sys & Increase AOT for Inoperable Load Shedding & Sequencing Sys from Eight to Twelve Hours ML20045H7111993-07-14014 July 1993 Application for Amend to License NPF-29,changing TS to Eliminate Previous Retrictions on Ensuring Operability of Igniters in Encl Areas & Igniters in Open Areas Adjacent to Inoperable Igniters & Redefining Hydrogen Ignition Sys ML20044F1571993-05-20020 May 1993 Proposed Amend PCOL-93/04 to License NPF-29,revising TS 4.8.3.1.2 & 4.8.3.2.2 to Remove Operability Requirements for auto-test Feature of Load Shedding & Sequencing (LSS) Sys & Increase AOT for Inoperable LSS Sys from Eight to 24 H ML20044F1621993-05-20020 May 1993 Proposed Amend PCOL-92/09 to License NPF-29,removing Unnecessary Operability Requirements for IRMs & APRMs During Plant Shutdown Conditions.Ts Changes Follow NUREG-1434, Rev 0 Requirements ML20116D1391992-10-29029 October 1992 Application for Amend to License NPF-29,consisting of Proposed Change,Revising TS Per Generic Ltr 88-16, Removal of Cycle Specific Parameter Limits from TS, That Will Change Each Fuel Cycle ML20118A5681992-09-14014 September 1992 Application for Amend to License NPF-29,deleting TS Tables 3.6.4-1 Re Containment & Drywell Isolation Valves, 3.6.6.2-1 Re Secondary Containment Ventilation Sys & 3.8.4.2-1 Re MOV Thermal Overload Protection,Per GL 91-08 ML20113H6001992-07-29029 July 1992 Application for Amend to License NPF-29,consisting of PCOL-92/03,changing Selected TS Instrumentation Surveillance Test Intervals & Allowed Outage Times,Based on Cited GE Repts ML20101B6681992-05-29029 May 1992 Application for Amend to License NPF-29,changing TS Bases 3/4.9.7, Crane Travel - Spent Fuel & Upper Containment Fuel Storage Pools ML20096B8861992-05-0606 May 1992 Application for Amend to License NPF-29,changing TS Re Primary Containment Penetration Conductor Overcurrent Protective Devices,Under Exigent Circumstances,Per Generic Ltr 89-10 ML20095K0351992-04-30030 April 1992 Application for Amend to License NPF-29,changing TS 3/4.3.1 Re Reactor Protection Sys instrumentation,3/4.3.6 Re Control Rod Block Instrumentation & 3/4.3.7.6 Re Source Range Monitors,Per Violations in Insp Rept 50-416/92-04 ML20095E7341992-04-22022 April 1992 Suppl to 910626 Application for Amend to License NPF-29, Modifying Wording of Requested Change to LCO 3.3.2,Action B Re Extension of Instrumentation Surveillance Intervals & Allowed Outage Times 1999-08-20
[Table view] Category:TEXT-LICENSE APPLICATIONS & PERMITS
MONTHYEARML20217F1951999-10-0707 October 1999 Application for Amend to License NPF-29,to Revise Licensing Basis to Credit One of Insights/Conclusions of NUREG-1465, Revised Source Term Insights ML20211E7061999-08-20020 August 1999 Application for Amend to License NPF-29,incorporating Many of Generic Improvements Agreed Upon Between Industry & NRC Since GGNS Conversion to ITS ML20196K0791999-06-29029 June 1999 Suppl to 980720 Application for Amend to License NPF-29, Implementing BWROG Enhanced Option I-A,reactor Stability long-term Solution.Rev to TS 3.4.1 Inadvertently Omitted from Original Application ML20196G6901999-06-23023 June 1999 Application for Amend to License NPF-29,revising TS Associated with Various Esfss Which Need No Longer Be Credited Following Design Basis Fuel Handling Accident ML20206K5241999-05-0606 May 1999 Application for Amend to License NPF-29,changing TSs Required to Support Ggns,Cycle 11 Operation,Including Slmcpr.Portions of Encl Re Addl Info on Calculated Cycle Specific SL MCPR for Plant Cycle 11 Withheld ML20206R9271999-01-12012 January 1999 Application for Amends to Licenses NPF-29 & NPF-47,proposing Required Actions Consistent with NRC Accepted Change to BWR Improved TS NUREG-1433 & NUREG-1434 ML20236T1551998-07-20020 July 1998 Application for Amend to License NPF-29,revising TSs Re BWROG Enhanced Option I-A Reactor Stability Long Term Solution ML20217P0241998-04-0606 April 1998 Amend 135 to License NPF-29,revising TSs for GGNS to Permit Implementation of Containment Leak Rate Testing Provisions of 10CFR50,App J,Option B ML20198J3451998-01-0909 January 1998 Revised Application for Amend to License NPF-29,providing Clarifications to Amend & Adding Restriction to Allowed Interval Extensions Re Option B of 10CFR50,app J ML20198N3851997-10-28028 October 1997 Application for Amend to License NPF-29,revising TS to Implement Option B & Ref SE Issued by NRR for Ggns'S App J Exemption as Implementing Document for performance-based Leakage Testing Program ML20210V5461997-09-18018 September 1997 Application for Amend to License NPF-29,reflecting Decrease of Two Recirculation Loop SLMCPR to 1.11 & Single Recirculation Loop SLMCPR Limit to 1.12.Proprietary Info Re SLMCPR for Cycle 10,encl.Proprietary Info Withheld ML20134E1191996-10-22022 October 1996 Application for Amend to License NPF-29,revising TS Figure 3.4.11-1, Minimum Reactor Vessel Metal Temperature Vs Reactor Vessel Pressure, Curves Using Methodology of Reg Guide 1.99,Rev 2, Radiation Embrittlement.. ML20117P4421996-09-19019 September 1996 Application for Amend to License NPF-29,changing Containment Purge Valves W/Resilient Seals on Performance Based Leakage Testing Frequency ML20117G6661996-08-27027 August 1996 Application for Amend to License NPF-29,modifying Tech Specs Surveillance Requirements for Safety/Relief Valves ML20116F0141996-07-31031 July 1996 Rev 1 to Application for Amend to License NPF-29,revising TSs Required to Support Cycle 9,reload 8.Rev 1 to J11-02863SLMCPR, GGNS Cycle 9 Safety Limit MCPR Analysis Encl.Rept Withheld ML20113B7341996-06-20020 June 1996 Application for Amend to License NPF-29,redefining Secondary Containment Boundary to Allow Encl Bldg to Be Inoperable During Upcoming Refueling Outage ML20112E1741996-05-31031 May 1996 Application for Amends to Licenses NPF-29 & NPF-47 Adding Addl Acceptable Required Actions to Tech Spec Limiting Condition for Operation (LCO) 3.9.1, Refueling Equipment Interlocks ML20117D6901996-05-0909 May 1996 Application for Amend to License NPF-29,revising TSs to Support Unit 1,cycle 9 Including Changes to SLMCPR & Ref for Analytical Methods Used to Determine Core Operating Limits ML20117F4541996-05-0909 May 1996 Application for Amend to License NPF-29,modifying SRV Surveillance Test for Relief Mode of Operation ML20111B2631996-05-0808 May 1996 Application for Amend to License NPF-29,placing Containment Purge Valves W/Resilient Seals on Performance Based Leakage Testing Frequency ML20108E3551996-05-0606 May 1996 Application for Amend to License NPF-29,changing Name from Mississippi Power & Light to Entergy Mississippi,Inc ML20107E2521996-04-18018 April 1996 Application for Amend to License NPF-29,prohibiting Performance of 24-h EDG Maint Run While Unit in Either Mode 1/2 RBG-42766, Application for Amends to Licenses NPF-29 & NPF-47,adding Addl Acceptable Method of Fuel Movement,Control Rods Removed or Withdrawn from Defueled Core Cells1996-04-18018 April 1996 Application for Amends to Licenses NPF-29 & NPF-47,adding Addl Acceptable Method of Fuel Movement,Control Rods Removed or Withdrawn from Defueled Core Cells ML20100J8311996-02-22022 February 1996 Application for Amend to License NPF-29,modifying Safety Setpoint to Tolerance Requirements for Safety/Relief Valves ML20097C3491996-02-0101 February 1996 Application for Amend to License NPF-29,revising TS Bases to Include Changes Since 950221 Approval of TS Bases RBG-42193, Rev to Application for Amend to License NPF-29 & Proposed Amend to License NPF-47,revising TS 3/4.6.2.2, Drywell Bypass Leakage1995-11-20020 November 1995 Rev to Application for Amend to License NPF-29 & Proposed Amend to License NPF-47,revising TS 3/4.6.2.2, Drywell Bypass Leakage ML20087B5031995-08-0101 August 1995 Application for Amend to License NPF-29,by Revising TS Assoc W/Various ESF Sys Following Design Fuel Handling Accident ML20086N2071995-07-21021 July 1995 Application for Amend to License NPF-29,proposing to Recapture Approx 2 1/2 Yrs of Low/No Power Operation by Extending 40-yr Operating License Term from 220616 to 241101 ML20078S4891995-02-14014 February 1995 Application for Amend to License NPF-29 Consisting of Changes to TS Requirements 4.4.1.4.a.1 & 4.6.1.4.a.2 ML20078N6481995-02-10010 February 1995 Application for Amend to License NPF-29,consisting of Mod to Proposed Amend to OL (PCOL-93/13),requesting to Perform Drywell Bypass Leakage Rate Surveillance on Performance Based Interval ML20079B4431994-11-0909 November 1994 Application for Amend to License NPF-29,revising TS Associated W/Various ESF Sys Following Design Basis Fuel Handling accident.Mark-up of Current Ts,Proposed TS & mark- Up Improved TS Encl ML20076F9781994-10-12012 October 1994 Application for Amend to License NPF-29,consisting of PCOL-94/01,closing & Deleting License Condition 2.C.(26) for Turbine Disc integrity.Mark-up of Affected OL Page & Proprietary Supporting Info Encl.Proprietary Info Withheld ML20069P4401994-06-17017 June 1994 Proposed Amend to OL (PCOL-94/02),removing License Conditions for EDGs Associated w/NUREG-1216 ML20059H6011994-01-13013 January 1994 Application for Amend to License NPF-29,consisting of Proposed Amend to OL PCOL-93/15,removing 2,324 Spent Fuel Pool Storage Limit & Allowing Full Use of Spent Fuel Storage Spaces ML20059A4801993-10-22022 October 1993 Application for Amend to License NPF-29,modifying Testing Frequencies for Drywell Bypass Test & Airlock Tests ML20059B0131993-10-15015 October 1993 Application for Amend to License NPF-29,converting Current GGNS TS to TS Based Largely on NUREG-1434,Rev 0 ML20056E2861993-08-17017 August 1993 Application for Amend to License NPF-29,proposing Changes to Amend TS Section 3/4.3.7.10, Loose Part Detection Sys by Relocating Loose Part Detection Instrumentation to Administrative Controls ML20046D2041993-08-11011 August 1993 Proposed Change to OL (PCOL-93/07) to License NPF-29, Amending TS Section 3/4.3.7.10, Loose Part Detection Sys by Relocating Locating Loose Part Detection Instrumentation from TS to Administrative Controls,Per NUREG-1434,Rev 0 ML20046D1911993-08-11011 August 1993 Proposed Change to OL (PCOL-93/06) to License NPF-29, Revising TS to Support Compliance W/New Requirements of 10CFR20 & 10CFR50.36a ML20056D5321993-08-11011 August 1993 Proposed Change to OL (PCOL-93/09) to License NPF-29, Amending TS Section 3/4.3.7.5 by Relocating Certain Accident Monitoring Instrumentation from TS to Administrative Control,Per NUREG-1434,Rev 0,w/respect to RG 1.97 ML20056C7131993-07-15015 July 1993 Application for Amend to License NPF-29,proposing Changes to Remove Operability Requirements for auto-test Feature of Load Shedding & Sequencing Sys & Increase AOT for Inoperable Load Shedding & Sequencing Sys from Eight to Twelve Hours ML20045H7111993-07-14014 July 1993 Application for Amend to License NPF-29,changing TS to Eliminate Previous Retrictions on Ensuring Operability of Igniters in Encl Areas & Igniters in Open Areas Adjacent to Inoperable Igniters & Redefining Hydrogen Ignition Sys ML20044F1571993-05-20020 May 1993 Proposed Amend PCOL-93/04 to License NPF-29,revising TS 4.8.3.1.2 & 4.8.3.2.2 to Remove Operability Requirements for auto-test Feature of Load Shedding & Sequencing (LSS) Sys & Increase AOT for Inoperable LSS Sys from Eight to 24 H ML20044F1621993-05-20020 May 1993 Proposed Amend PCOL-92/09 to License NPF-29,removing Unnecessary Operability Requirements for IRMs & APRMs During Plant Shutdown Conditions.Ts Changes Follow NUREG-1434, Rev 0 Requirements ML20116D1391992-10-29029 October 1992 Application for Amend to License NPF-29,consisting of Proposed Change,Revising TS Per Generic Ltr 88-16, Removal of Cycle Specific Parameter Limits from TS, That Will Change Each Fuel Cycle ML20118A5681992-09-14014 September 1992 Application for Amend to License NPF-29,deleting TS Tables 3.6.4-1 Re Containment & Drywell Isolation Valves, 3.6.6.2-1 Re Secondary Containment Ventilation Sys & 3.8.4.2-1 Re MOV Thermal Overload Protection,Per GL 91-08 ML20113H6001992-07-29029 July 1992 Application for Amend to License NPF-29,consisting of PCOL-92/03,changing Selected TS Instrumentation Surveillance Test Intervals & Allowed Outage Times,Based on Cited GE Repts ML20101B6681992-05-29029 May 1992 Application for Amend to License NPF-29,changing TS Bases 3/4.9.7, Crane Travel - Spent Fuel & Upper Containment Fuel Storage Pools ML20096B8861992-05-0606 May 1992 Application for Amend to License NPF-29,changing TS Re Primary Containment Penetration Conductor Overcurrent Protective Devices,Under Exigent Circumstances,Per Generic Ltr 89-10 ML20095K0351992-04-30030 April 1992 Application for Amend to License NPF-29,changing TS 3/4.3.1 Re Reactor Protection Sys instrumentation,3/4.3.6 Re Control Rod Block Instrumentation & 3/4.3.7.6 Re Source Range Monitors,Per Violations in Insp Rept 50-416/92-04 1999-08-20
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BEFORE THE UNITED STATES NUCLEAR REGULATORY COMMISSION LICENSE NO. NPF-29 DOCKET NO. 50-416 IN THE MATTER OF MISSISSIPPI POWER & LIGHT COMPANY and MIDDLE SOUTH ENERGY, INC.
and SOUTH MISSISSIPPI ELECTRIC POWER ASSOCIATION AFFIRMATION I, O. D. Kingsley, Jr., being duly sworn, stated that I am Vice President, Nuclear Operations of Mississippi Power & Light Company; that on
. behalf of Mississippi Power & Light Company, Middle South Energy, Inc., and South Mississippi Electric Power Association I am authorized by Mississippi Power & Light Company to sign ~and file with the Nuclear Regulatory Commission, this application for amendment of the Operating License of the Grand Gulf Nuclear Station; that I signed this application as Vice President, Nuclear
. Operations of Mississippi Power & Light Company; and that the statements made and the matters set forth therein are true and correct to t best of my knowledge,.information and belief.
. /
"O , D .' Kin ' 1 STATE OF MISSISSIPPI COUNTY OF HINDS SUBSCRIBED AND SWORN To bef re me, a Notar Public, in and for the County and State above named, this day of , 1985.
(SEAL) b Notary Public (f
My commission expires:
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J0P13AECM85042904 - 4
SUBJECT:
NLS-84/05 Technical Specifications 5.6.1.b and 5.6.3, page 5-6 DISCUSSION:
It is proposed to change the nominal center-to-center distance between fuel assemblies placed in the storage racks in the GGNS spent fuel storage pools from 12 inches to 6.26 inches and to change the maximum spent fuel storage capacity at GGNS from 1270 fuel assemblies in the spent fuel storage pool to 4348 fuel assemblies in the spent fuel pool and 800 fuel assemblies in the upper containment pool. This change will accommodate the proposed replacement of the current GGNS low density aluminum spent fuel storage racks with Joseph Oat Corporation designed / constructed high density spent fuel storage racks.
NRC has currently licensed GGNS Unit I with a capacity of 170 fuel storage assemblies in the upper containment pool. The capacity of these fuel storage racks are not addressed in Section 5 of the current technical specifications. MP&L is including the upper containment pool fuel storage racks in this proposal as a conservative measure and for completeness.
JUSTIFICATION:
GGNS was designed with two spent fuel storage pools. One is adjacent to the reactor cavity inside containment, hereinafter referred to as the
" upper containment pool," and was designed for storage of spent fuel during refueling activities and other special evolutions, until such time as it could be moved to longer term storage in the other pool or replaced in the reactor vessel during core reload. The second pool, hereinafter referred to as the " spent fuel pool," is located in the auxiliary building and was designed for longer term storage of spent fuel during reactor operation until such time as it could be packaged and shipped to a reprocessing facility. The combined design capacity of these pools is 1440 spaces (approximately 1.8 full cores). The CGNS Final Safety Analysis Report addresses the safety implications of these pools to include relevant parameters associated with criticality, structural integrity, and cooling (Safety Evaluation, Docket No. 50-416). The evaluation found the environmental and safety impacts of such storage to be acceptable.
On April 17, 1977, the federal government issued a policy statement on commercial reprocessing of spent nuclear fuel which effectively eliminated reprocessing as part of the relatively near term nuclear fuel cycle. On October 18, 1977, the Generic Environmental Statement on Mixed Oxide fuels (CESMO) proceedings were deferred indefinitely. The combined effect of this national policy was to leave operating nuclear plants, like GCNS, without a repository for the spent fuel previously generated or being generated. Thus, MP&L has essentially no alternative except for reracking of the GGNS spent fuel pools to further increase its storage capacity.
With this application, MP&L is requesting approval to use Joseph Oat Corporation designed / constructed high density spent fuel racks to increase the Grand Gulf Nuclear Station (GGNS) spent fuel pool capacity to 5148 J0Pl4 MISC 85041801 - 1
.n total spent fuel storage spaces - 800 spaces in the upper containment pool and 4348 spaces in the spent fuel pool. This modification would extend the GGNS fuel storage capability from the current 1990 date to the year 2004.
The increase in GGNS spent fuel storage capacity would be accomplished by replacing the existing low density non-poison racks with neutron absorbing high density _ racks.
The' analysis summary supporting the proposed amendment request is set forth in Attachment 2. This analysis addresses the applicable requirements set forth in the NRC's Guidance on Spent Fuel Pool Modifications dated April 14, 1978 (revised January 18, 1979).
SIGNIFICANT HAZARDS CONSIDERATION:
Mississippi Power and Light (MP&L) has made the determination that this amendment request involves no significant hazards considerations by evaluating it in accordance with the requirements of 10 CFR 50.92. This ensures that operation of the facility 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.
The following evaluation demonstrates by reference to the analysis summary contained in Attachment 2 that not one of the three significant safety hazards consideration guidelines are met. Each of the three standards is discussed below, o First Standard Operation of-the facility in accordance with the proposed amendment would not involve a significant increase in the probability or consequences of an accident previously evaluated.
The analysis of this proposed reracking has been accomplished using current NRC Staff accepted codes and standards. The results of the analysis meet the specified acceptance criteria set forth in these standards.
From our analyses and regulatory document reviews, MP&L has identified the following potential accident scenarios: 1) fuel damage from an equipment drop onto the spent fuel;E2) thermal-hydraulic concerns of fuel pool cooling; 3) seismic event; 4) spent fuel assembly drop; 5) and natural disaster. The probability of occurrence of any of these accidents is not affected by the racks themselves; therefore, reracking will not increase the probability of occurrence of these accidents.
J0P14 MISC 85041801 - 2
.The consequences of the equipment drop accident have been evaluated
-with conclusions on page 7-6 of Attachment 2. The cask handling
^
crane stops'and administrative controls will continue to be used to prevent heavy ~1oads-and casks from being moved.into the fuel pool
~
area; therefore, the spent fuel cask drop accidentzis not credible and was not evaluated.. Thus, the consequences of this type accident will not be significantly increased from previous analyses as
. described in the GGNS FSAR section 15.7.4.3.
- The thermal-hydraulic concerns of fuel pool cooling have been evaluated (Section 5 of Attachment 2). As indicated in Table 5.2.1
'(page 5-18 of Attachment 2), neither the peak local coolant temperature nor the peak local cladding temperature significantly
. increases due to the increased density of spent fuel in the pool resulting from the proposed high density racks modification. The consequences of a loss of fuel pool' cooling' accident will not be significantly increased from previously evaluated accidents by the
. installation of proposed high density racks.
The consequences of a seismic event have been evaluated. The
^
proposed high density racks were evaluated against the appropriate NRC
-standards,aGGNS FSAR, and applicable codes. The results of the seismic and structural analysis show that the proposed racks meet all
, .of the NRC structural acceptance criteria and are consistent with licensing reports on high density fuel racks _ submitted by Fermi II and Quad Cities nuclear stations, as indicated on page 6-1 of Attachment 2. Thus, the consequences of seismic events will not significantly increase from previously evaluated seismic events.
The consequences of a spent fuel assembly drop accident are described on page 4-14 and Section 7 of Attachment 2. The radiological consequences for this type accident are unchanged from previous analyses presented in the GCNS FSAR Section 15.7.4.3, and K,ff is shown to always be less than the NRC acceptance criteria of 0.95.
Thus, the consequences of this type accident will not be signi-ficantly increased from previously evaluated spent fuel assembly-drop p accidents.
The fuel storage facilities are designed to seismic Category I
- requirements to prevent earthquake damage to the stored fuel as F stated on page 6-1 of Attachment 2. From the analysis it has been determined that the spent fuel storage arrangement and design meet-
,_ the safety design bases and satisfy the intent of Regulatory Guide l.13 which is intended to preclude any deleterious effects on spent i' fuel storage integrity due to natural phenomena such'as' earthquakes, l ternadoes, hurricanes,-and floods. Therefore, the consequences of a natural disaster accident will not significantly increase from previously evaluated natural disaster analyses.
I By the above rationale MP&L believes that the proposed GGNS spent
, , fuel pool high density racks will not involve a significant increase l
n J0P14 MISC 85041801 3 11
I e, s.
'P .
in the. probability or consequences of an accident previously
"~
_ evaluated, e;
o Second Standard.
Operationof'thelfacilityinaccordancewith the proposed; amendment would not create the
'1 possibility'of a new or different kind of
- accident from any accident previously evaluated. "
IMP &L.has evaluated.the proposed reracking in~accordance with-the "NRC Position for' Review and Acceptance of Spent Fuel Storage and Handling
--Applications", appropriate NRC Regulatory Guides, appropriate sections in the NRC Standard Review Plan,'and appropriate industry codes and standards. Based upon MP&L's analysis and review of NRC evaluations and industry standards and codes, MP&L believes that the proposed-reracking does not in any way create the possibility of a new or different kind of accident than those previously evaluated.
oi Third Standard Operation of the facility in accordance with the proposed amendment would not involve a significant reduction in a. margin.of safety.
Consideration of the' issue of' margin of safety'when applied to a reracking-modification requires the following areas to be addressed
'(as established by the NRC Staff safety evaluation review process):
- 1. Nuclear criticality considerations,
- 2. Thermal-hydraulic considerations,
,-3. -Mechanical, material, and structural considerations.
f
!' LThe margin of safety that has been_ established for nuclear
! criticality considerations is that the neutron multiplication factor
, in the spent fuel. pool remains:less.than or equal to 0.95, including all uncertainties under all conditions. The criticality analysis for the proposed modification is' discussed in Section 4 of Attachment 2..
i: The methods utilized in the analysis conform with ANSI N18.2-1973/
f " Nuclear Safety Criteria for the Design of Stationary Pressurized
.Water Reactor Plants"; ANSI N210-1976,~" Design Objectives for LWR
,, Spent Fuel Storage Facilities at Nuclear Power Stations"; Regulatory Guide 3.41, " Validation of Calculational Methods for Nuclear Criticality Safety" (and related ANSI N16.9-1975); NRC Standard Review Plan, Section 9.1.2, " Spent Fuel Storage"; and the NRC guidance, "NRC Position for Review and Acceptance of Spent Fuel Storage and Handling Applications."
J0P14 MISC 85041801 - 4 i
~
-f
,p *
.+
a The results of this analysis-indicate-that K,ff is always less than
- 0.95~ including all. uncertainties at a 95/95 probability / confidence 11evel thereby meeting-the acceptance criteria for criticality.
Minimum designirequirements for poison concentrations are discussed in Section 4.4.31of Attachment 2.. Aspects of the construction-cprocesssand quality assurance: controls which establish confidence
- that the minimum poison requirements are' met in the high density
- rackstare-discussed.in, Attachment 3 to this submittal. The retention of. poison material will be monitored by'a surveillance program at each refueling outage. This program.is described in Section 10 of Attachment.2.. MP&L has concluded'that proposed high density racks do
> not involve ~a significanttreduction in the= margin:of safety for nuclear criticality.
, _When evaluating thermal-hydraulics concerns, the areas addressed to determine if there is a significant reduction in a margin of safety J
are: 1) maximum fuel temperature, and 2) the increase in temperature of the water in the pool. The. thermal-hydraulic evaluation is described in Section 5 of Attachment 2. Results of these analyses show that fuel cladding t'emperatures under' abnormal conditions are.
sufficiently low to preclude. failures and that boiling does not s occur. In addition, the existing spent fuel cooling system as.
modified per Operating License Conditions 2.C(20) and (21), will provide the capacity to maintain-an' acceptable temperature range for normal and abnormal heat loads. The cooling system is described in the GGNS FSAR Section 9.1.3. Thus,-there is no significant reduction-
_ in the margin of safety from a thermal-hydraulic standpoint or from a e spent fuel cooling standpoint.
The mechanical, material,'and structural considerations ~of the
. proposed high density racks are described in Attachment 2. The racks are designed in accordance with "NRC Position for Review and Acceptance of Spent Fuel Storage and Handling Applications" dated
' April 14, 1978 and revised January 18, 1979. The racks are designed r 'to Seismic Category 1 requirements and are classified as ANS Safety Class 3 and constructed to ASME Code Class 3 Component Support-Structures'except where the weld stresses are less than twenty (20) percent of yield in which' case the vendor visual inspection criteria was applied in lieu of NF.. visual inspection criteria. 'The racks are designed to withstand loads which may result from fuel handling accidents and from the maximum uplift force of the fuel handling crane. .The materials utilized are compatible with the spent fuel pool environment and the spent fuel assemblies. The' structural
-considerations of'the racks provide a' sufficient margin of safety against tilting and sliding such that the racks do not impact each
. other or impact the pool walls. . Structural integrity of the pool structure =is maintained with additional dead load, live load, thermal load, wind load, and seismic load considerations; therefore, the margin of safety is not.significantly reduced by the proposed high density racks..
J0P14 MISC 85041801 - S
v.-
, hs ac '
- s-9 MP&L. believes-that the proposed GGNS spent-fuel pool high density racks modification-does not:
, 51); Involve a significant increase in the probability er 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) LInvolve a significant reduction in a margin of safety.
As such,'MP&L has' determined and submits that the proposed high
- density racks modification described herein does not involve a
, significent hazard.
. ENVIRONMENTAL CONSIDERATION:
MP&L.has evaluated the proposed high density racks modification in accordance with the requirements of 10 CFR 51.5 and has found that the l proposed high density' racks'do not involve an environmental consideration.-
In MP&L's analysis and review of NRC evaluations,' regulatory documents, and related industry experience, MP&L finds, as indicated in Section 9 of-Attachment-2, that the proposed-high density racks modification does not
~
involve:
- 1) a _ matter which may result 1Ln a significant increase in any adverse environmental impact previously evaluated in the Final Environmental Statement (FES) as modified by the NRC staff's
, ' testimony to the Atomic Safety and Licensing Board (ASLB),
supplements to the FES, environmental impact appraisals, or in any decisions of the ASLB; or 2)' a significant change in effluents or power level.(in accordance with 10CFR51.5(b)(2)); .or
- 3) a matter not previously reviewed and evaluated in the documents specifiedfin _(1) above, which may have a significant adverse -
-environmental impact.
- Therefore,'MP&L has determined and submits that the proposed high density
. racks do not' involve an environmental consideration.
J0P14 MISC 85041801 - 6 o