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Initiation
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Results
Other: AECM-82-492, Requests That License Condition 2.C.(44)(i)(a) Be Revised to Require Submittal Re Automatic Depressurization Sys Logic Mods by 821215.Previous Submittal Date of 821029 Erroneously Requested Due to Revised BWR Owners Group Schedule, AECM-82-603, Comments on BWROG-8260, NUREG-0737,Item II.K.3.18,Mod of Automatic Depressurization Sys Logic. Option 4,providing Bypass Timer Delay,Will Assure Adequate Core Cooling During Worst Case Conditions, AECM-85-0014, Forwards Addl Info,Requested in ,Re Concerns Involving Transfer of Control to Remote Shutdown Panel Resulting in Change in Operating Status of Load That May Be Detrimental to Safe Shutdown, AECM-85-0341, Forwards Addl Info Re ECCS Performance Analysis Which Supports Increase in Peak Cladding Temp of 51 F Compared to Current FSAR Analysis,Per Request.Fsar Changes Will Be Made If Design Change Implemented, AECM-85-0396, Advises That Tech Spec Changes Contained in Amends 4 & 6 to License NPF-29 Will Be Effective Before Startup After First Refueling Outage,Per 850918 & 1021 Requests, AECM-86-0006, Forwards Technical Justification for Proposal to Delete Peak Recording Accelerographs Currently Installed on Reactor Piping Locations,Per Section 16.3.1 of Sser 6 (NUREG-0831).Response by 860228 Requested.Fee Paid, AECM-86-0234, Forwards Clarification Re Proposed Mod to License Condition 2.C(20) Concerning Standby Svc Water Sys, AECM-86-0329, Submits List of Affected Tech Spec Pages,Effective Dates & Associated Amend Numbers,In Response to NRC 860827 & 1006 Requests, AECM-86-0332, Advises of Effective Dates for Amends 6 & 8 to License NPF-29 for Listed Tech Specs,In Response to 851021 & 860827 Requests, ML20133P171, ML20154R546, ML20155J934, ML20209D136, ML20209D152
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MONTHYEARAECM-82-492, Requests That License Condition 2.C.(44)(i)(a) Be Revised to Require Submittal Re Automatic Depressurization Sys Logic Mods by 821215.Previous Submittal Date of 821029 Erroneously Requested Due to Revised BWR Owners Group Schedule1982-10-21021 October 1982 Requests That License Condition 2.C.(44)(i)(a) Be Revised to Require Submittal Re Automatic Depressurization Sys Logic Mods by 821215.Previous Submittal Date of 821029 Erroneously Requested Due to Revised BWR Owners Group Schedule Project stage: Other AECM-82-603, Comments on BWROG-8260, NUREG-0737,Item II.K.3.18,Mod of Automatic Depressurization Sys Logic. Option 4,providing Bypass Timer Delay,Will Assure Adequate Core Cooling During Worst Case Conditions1982-12-14014 December 1982 Comments on BWROG-8260, NUREG-0737,Item II.K.3.18,Mod of Automatic Depressurization Sys Logic. Option 4,providing Bypass Timer Delay,Will Assure Adequate Core Cooling During Worst Case Conditions Project stage: Other AECM-85-0014, Forwards Addl Info,Requested in ,Re Concerns Involving Transfer of Control to Remote Shutdown Panel Resulting in Change in Operating Status of Load That May Be Detrimental to Safe Shutdown1985-01-17017 January 1985 Forwards Addl Info,Requested in ,Re Concerns Involving Transfer of Control to Remote Shutdown Panel Resulting in Change in Operating Status of Load That May Be Detrimental to Safe Shutdown Project stage: Other ML20151L0531985-07-12012 July 1985 Application for Amend to License NPF-29,revising Tech Specs to Reflect Organizational Changes & Addition of Two Primary Containment Penetration Conductor Overcurrent Protection Circuit Breakers Project stage: Request ML20133P1711985-08-12012 August 1985 Proposed Tech Specs,Reflecting Design Changes & Editorial Clarification Re Leak Rate Testing of RHR to Head Spray Isolation Valve & ECCS Actuation Instrumentation Project stage: Other AECM-85-0228, Application for Amend to License NPF-29,changing Tech Specs to Reflect Design Changes & Editorial Clarifications.Fee Paid1985-08-12012 August 1985 Application for Amend to License NPF-29,changing Tech Specs to Reflect Design Changes & Editorial Clarifications.Fee Paid Project stage: Request AECM-85-0248, Withdraws 850712 Proposed Change to License NPF-29,Item 7,to Reduce Burden of Requiring Rev to OL W/Each Tech Spec Amend. Change Inconsistent W/Past NRC Practices & Procedures1985-08-12012 August 1985 Withdraws 850712 Proposed Change to License NPF-29,Item 7,to Reduce Burden of Requiring Rev to OL W/Each Tech Spec Amend. Change Inconsistent W/Past NRC Practices & Procedures Project stage: Request ML20133A7611985-09-25025 September 1985 Proposed Changes to Tech Specs 6.3.1 & 6.4.1,providing Justification for Exemption from Requirements for Senior Reactor Operator Qualifications Project stage: Request AECM-85-0304, Application for Amend to License NPF-29,supplementing 850812,23 & 30 Submittals,To Provide Justification for Exemption from Tech Spec 6.3.1 & 6.4.1 Requirements for Senior Reactor Operator Qualifications1985-09-25025 September 1985 Application for Amend to License NPF-29,supplementing 850812,23 & 30 Submittals,To Provide Justification for Exemption from Tech Spec 6.3.1 & 6.4.1 Requirements for Senior Reactor Operator Qualifications Project stage: Supplement AECM-85-0314, Provides Addl Info to Support Proposed Change to Tech Specs 4.1.3.3.b.1.b.GE Info Ltr Entitled Hydraulic Control Unit Accumulator Pressure Switches, to Support Proposed Change,Encl1985-09-26026 September 1985 Provides Addl Info to Support Proposed Change to Tech Specs 4.1.3.3.b.1.b.GE Info Ltr Entitled Hydraulic Control Unit Accumulator Pressure Switches, to Support Proposed Change,Encl Project stage: Request AECM-85-0305, Forwards Resumes of Two Individuals Appointed as Supervisors to Organization Radiation Control Function,Per Request for Addl Info Re 850712 Proposed Change to Tech Spec Figure 6.2.2.-11985-10-0202 October 1985 Forwards Resumes of Two Individuals Appointed as Supervisors to Organization Radiation Control Function,Per Request for Addl Info Re 850712 Proposed Change to Tech Spec Figure 6.2.2.-1 Project stage: Request AECM-85-0306, Responds to Request for Addl Info Re 850812 Application for Amend to License NPF-29.Prompt Resolution of Questions & Approval of Previously Submitted Tech Specs Needed for Outage Scheduled to Start on 8510121985-10-0505 October 1985 Responds to Request for Addl Info Re 850812 Application for Amend to License NPF-29.Prompt Resolution of Questions & Approval of Previously Submitted Tech Specs Needed for Outage Scheduled to Start on 851012 Project stage: Request AECM-85-0341, Forwards Addl Info Re ECCS Performance Analysis Which Supports Increase in Peak Cladding Temp of 51 F Compared to Current FSAR Analysis,Per Request.Fsar Changes Will Be Made If Design Change Implemented1985-10-22022 October 1985 Forwards Addl Info Re ECCS Performance Analysis Which Supports Increase in Peak Cladding Temp of 51 F Compared to Current FSAR Analysis,Per Request.Fsar Changes Will Be Made If Design Change Implemented Project stage: Other ML20137Q8901985-11-22022 November 1985 Forwards Safety Evaluation Re 850812 Request for Amend to License NPF-29,adding Pressure Permissive Interlocks to Control Circuits for Low Pressure ECCS Injection Valves,Item 13 of 850812 Request Should Be Revised Project stage: Approval ML20137Q8971985-11-22022 November 1985 Safety Evaluation Re Low Pressure ECCS Sys Pressure Permissive Interlocks.Exceeding ASME Code Allowable Design Pressure for Interlocks Unacceptable Project stage: Approval AECM-85-0396, Advises That Tech Spec Changes Contained in Amends 4 & 6 to License NPF-29 Will Be Effective Before Startup After First Refueling Outage,Per 850918 & 1021 Requests1985-12-0606 December 1985 Advises That Tech Spec Changes Contained in Amends 4 & 6 to License NPF-29 Will Be Effective Before Startup After First Refueling Outage,Per 850918 & 1021 Requests Project stage: Other AECM-86-0006, Forwards Technical Justification for Proposal to Delete Peak Recording Accelerographs Currently Installed on Reactor Piping Locations,Per Section 16.3.1 of Sser 6 (NUREG-0831).Response by 860228 Requested.Fee Paid1986-01-10010 January 1986 Forwards Technical Justification for Proposal to Delete Peak Recording Accelerographs Currently Installed on Reactor Piping Locations,Per Section 16.3.1 of Sser 6 (NUREG-0831).Response by 860228 Requested.Fee Paid Project stage: Other ML20154R5461986-03-21021 March 1986 Proposed Tech Specs Revising License Condition 2.C.(28) Re Requirement for Corporate Mgt Officials on Nuclear Operations Staff & Modifying Tables 3.3.7.2-1 & 4.3.7.2-1 to Reflect Design Change Project stage: Other AECM-86-0082, Supplemental Application for Amend to License NPF-29, Modifying 851114 Proposed Change Re License Condition 2.C.(28) & Revising Tech Specs Concerning Design Changes to Be Implemented During First Refueling Outage.Fee Paid1986-03-21021 March 1986 Supplemental Application for Amend to License NPF-29, Modifying 851114 Proposed Change Re License Condition 2.C.(28) & Revising Tech Specs Concerning Design Changes to Be Implemented During First Refueling Outage.Fee Paid Project stage: Supplement ML20155D8101986-04-0808 April 1986 Summary of 860401 Meeting W/Utils Re Resolution of Issue of Interlocks for ECCS Injection Valves Which Also Function as Pressure Isolation Valves.Viewgraphs & List of Attendees Encl Project stage: Meeting ML20155J9341986-05-19019 May 1986 Proposed Tech Specs Adding Undervoltage Protection Device & Emergency Override of Test Mode for Div 3 HPCS Diesel Generator & Increasing Test Loads for Div 1 & 2 Batteries Project stage: Other AECM-86-0150, Application for Amend to License NPF-29,adding Another Undervoltage Protection Device & Emergency Override of Test Mode for Div 3 Diesel Generator & Increasing Test Loads for Div 1 & 2 Batteries.Fee Paid1986-05-19019 May 1986 Application for Amend to License NPF-29,adding Another Undervoltage Protection Device & Emergency Override of Test Mode for Div 3 Diesel Generator & Increasing Test Loads for Div 1 & 2 Batteries.Fee Paid Project stage: Request ML20205S2151986-05-27027 May 1986 Safety Evaluation Supporting Util 860110 Proposal to Remove Four Peak Recording Accelerographs Mounted on Reactor Piping Project stage: Approval ML20205S2021986-05-27027 May 1986 Forwards Safety Evaluation Supporting Util 860110 Proposal to Remove Four Peak Recording Accelerographs Installed on Reactor Piping Due to Inoperability Caused by Operating Transients & Adequacy of Other Seismic Instrumentation Project stage: Approval AECM-86-0111, Forwards Supplemental Info Re Design Change to Add Interlocks to ECCS Injection Valves,Per NRC 860403 Telcon. Approval of 850812 Proposed Amend to Tech Specs Also Requested1986-05-30030 May 1986 Forwards Supplemental Info Re Design Change to Add Interlocks to ECCS Injection Valves,Per NRC 860403 Telcon. Approval of 850812 Proposed Amend to Tech Specs Also Requested Project stage: Supplement AECM-86-0163, Provides Addl Info to 860321 Proposed Change PCOL-86/04 to License NPF-29 Re Mods to Automatic Depressurization Sys Per BWR Owners Group Evaluation of NUREG-0737,Item II.K.3.18. Info Clarifies Changes Made to Sys Initiation Circuitry1986-05-30030 May 1986 Provides Addl Info to 860321 Proposed Change PCOL-86/04 to License NPF-29 Re Mods to Automatic Depressurization Sys Per BWR Owners Group Evaluation of NUREG-0737,Item II.K.3.18. Info Clarifies Changes Made to Sys Initiation Circuitry Project stage: Request AECM-86-0221, Application for Amend to License NPF-29,changing Tech Spec Seismic Monitoring Instrumentation Tables to Delete four- Peak Recording Accelerographs on Reactor Piping & Make Measurement Values Consistent.Fee Paid1986-07-15015 July 1986 Application for Amend to License NPF-29,changing Tech Spec Seismic Monitoring Instrumentation Tables to Delete four- Peak Recording Accelerographs on Reactor Piping & Make Measurement Values Consistent.Fee Paid Project stage: Request ML20207E7261986-07-15015 July 1986 Proposed Changes to Tech Spec Seismic Monitoring Instrumentation Tables 3.3.7.2-1 & 4.3.7.2-1 to Delete four- Peak Recording Accelerographs on Reactor Piping & Make Measurement Values Consistent Project stage: Request AECM-86-0234, Forwards Clarification Re Proposed Mod to License Condition 2.C(20) Concerning Standby Svc Water Sys1986-07-25025 July 1986 Forwards Clarification Re Proposed Mod to License Condition 2.C(20) Concerning Standby Svc Water Sys Project stage: Other AECM-86-0232, Forwards Tabulation & Analyses for Standby Svc Water Cooling Towers Based on Max 30-day Average Wet Bulb & Refueling Outage 18,per NRC Request for Worst Case Scenario of Util 860519 Analyses1986-07-29029 July 1986 Forwards Tabulation & Analyses for Standby Svc Water Cooling Towers Based on Max 30-day Average Wet Bulb & Refueling Outage 18,per NRC Request for Worst Case Scenario of Util 860519 Analyses Project stage: Request ML20209D1521986-08-28028 August 1986 Notice of Consideration of Issuance of Amend to License NPF-29 & Proposed NSHC Determination & Opportunity for Hearing Re Addition of Specs to Table 3.3.3-1, ECCS Actuation Instrumentation Project stage: Other ML20209D1361986-09-0202 September 1986 Requests Notice of Consideration of Issuance of Amend to License NPF-29 & Proposed NSHC Determination & Opportunity for Hearing Re Addition of Specs to Table 3.3.3-1, ECCS Actuation Instrumentation Be Expeditiously Published in Fr Project stage: Other AECM-86-0329, Submits List of Affected Tech Spec Pages,Effective Dates & Associated Amend Numbers,In Response to NRC 860827 & 1006 Requests1986-10-14014 October 1986 Submits List of Affected Tech Spec Pages,Effective Dates & Associated Amend Numbers,In Response to NRC 860827 & 1006 Requests Project stage: Other AECM-86-0332, Advises of Effective Dates for Amends 6 & 8 to License NPF-29 for Listed Tech Specs,In Response to 851021 & 860827 Requests1986-10-17017 October 1986 Advises of Effective Dates for Amends 6 & 8 to License NPF-29 for Listed Tech Specs,In Response to 851021 & 860827 Requests Project stage: Other 1986-01-10
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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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MISSISSIPPI POWER & LIGHT COMPANY
] Helping Build Mississippi EdhMhMMd5 P. O. B O X 16 4 0. J A C K S O N, MISSISSIPPI 39215-1640 May 19, 1986 O. D. KING 5 LEY, JR.
vt(E PREllDENT NUCLE AR OPE A ATIONS U. S. Nuclear Regulatory Commission Office of Nuclear Reactor Regulation Washington, D. C. 20555 Attention: Mr. Harold R. Denton, Director
Dear Mr. Denton:
SUBJECT:
Grand Gulf Nuclear Station Unit 1 Docket No. 50-416 License No. NPF-29 File: 0260/0840/L-860.0 Proposed Amendment to the Operating y License (PCOL-86/09)
AECM-86/0150 In accordance with the provisions of 10 CFR 50.59 and 50.90, Mississippi Power & Light Company (MP&L) requests an amendment to License NPF-29, for Grand Gulf Nuclear Station (GGNS) Unit 1.
Attachment 1 to this letter contains proposed changes to Operating License NPF-29 as follows:
o The addition of another undervoltage protection device and emergency override of the test mode for the Division 3 diesel generator.
o Modification of Loop A of the Standby Service Water (SSW) system to provide design flows to all essential components.
o Provide a method for validating End-of-Cycle Recirculation Pump Trip system arc suppression time.
o Increasing the test loads for the Division 1 and 2 batteries.
In a letter from Mr. O. D. Kingsley, Jr. to Mr. Harold R. Denton dated August 23, 1985, MP&L committed to provide the NRC with SSW heat load and inventory calculations prior to the first refueling outage. Attachment 2 to this letter provides an analysis that demonstrates, upon completion of planned modiOcations to SSW loop A at the first refueling outage, the SSW system will meet the criteria of Regulatory Guide 1.27. This analysis assumes an operable siphon between SSW Basins A and B and does include the peak heat load associated with the high density fuel racks.
fh l) wp y/SO 00 o\
J10AECM86051403 - 1 Member Middle South Utilities System W
- AECM-86/0150 Page 2 In accordance with the provisions of 10 CFR 50.30, three (3) signed
- originals and forty (40) copies of the requested amendment are enclosed. The attachment provides the complete technical justification and discussion to
- support the requested amendment. This amendment has been reviewed and accepted i
by the Plant Safety Review Committee (PSRC) and the Safety Review Committee (SRC).
Based on the guidelines presented in 10 CFR 50.92, it is the opinion of 1 MP&L that this proposed amendment involves no significant hazards considerations.
In accordance with the requirements of 10 CFR 170.21, we have determined that the application fee is $150. A remittance of $150 is attached to this letter.
Yours ly, s
ODK:lm .
Attachments: GGNS PCOL-86/09 SSW Analysis Summary cc: Mr. T. H. Cloninger (w/a)
- Mr. R. B. McGehee (w/a)
Mr. N. S. Reynolds (w/a)
) Mr. H. L. Thomas (w/o)
Mr. R. C. Butcher (w/a)
Mr. James M. Taylor, Director (w/a)
Office of Inspection & Enforcement U. S. Nuclear Regulatory Commission i Washington, D. C. 20555 Dr. J. Nelson Grace, Regional Administrator (w/a)
U. S. Nuclear Regulatory Commission Region II 101 Marietta St., N. W., Suite 2900 Atlanta, Georgia 30323 Dr.AltonB.Cobb(w/a)
State Health Officer State Board of Health Box 1700 Jackson, Mississippi 39205 l
i J10AECM86051403 - 2
BEFORE THE UNITED STATES NUCLEAR REGULATORY COMMISSION LICENSE NO. NPF-29 DOCKET N0. 50-416 IN THE' MATTER OF MISSISSIPPI POWER & LIGHT COMPANY and MIDDLE SOUTH ENERGY, INC.
and SOUTH MISSISSIPPI ELECTRIC POWER ASSOCIATION AFFIRMATION I, 0. 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.
\
- h &N*
- 1. D.' Ki n s 1 J.
STATE OF. MISSISSIPPI COUNTY OF HINDS i- SUBSCRIBED AND SWORN T0 befor me, a Notary Public, in and for the County and State above named, this /- ay of C/)ana , 1986.
l (SEAL)
/(
'ML1a 0- AW Notary Public l
My commission expires:
N/ Cormthin Dpires Sep. 21, 1981 J10AECM86051403 - 5 .
Attachment 1 to AECM-86/0150
- 1. NPE-86/08
SUBJECT:
Technical Specification Tables 3.3.3-1, 3.3.3-2, and 4.3.3.1-1 pages 3/4 3-29, 32, 35. Technical Specification 4.8.1.1.2.d.12 page 3/4 8-6.
DISCUSSION: The proposed technical specification changes result from design changes to the plant'to add'an additional undervoltage protection device and emergency override of the test mode for the Division 3 HPCS diesel generator.
As done on several recent Technical Specification changes involving design changes to the Plant, it is requested that the NRC issue the changes with an open effective date and require that MP&L notify the NRC within 30 days of the effective date of implementation of the affected technical specification changes. This design change is scheduled for implementation not later than startup following the first refueling outage.
JUSTIFICATION: Mississippi Power & Light committed to add an additional undervoltage protection device and to provide an emergency override of the test mode for the Division 3 diesel generator in a letter to Mr. Harold R. Denton from L. F. Dale dated July 3, 1984 (AECM-84/0326), and these commitments were subsequently placed in Facility Operating License NPF-29 as Operating License Conditions 2.C.(37) a and b. Attached to this proposed change is a drawing showing arrangement and function of the new system components.
The first part of the proposed change provides an additional undervoltage protection device. This undervoltage protection consists of two specific elements, one associated with non-accident conditions and the other associated with accident conditions. This design change installs a new first level of undervoltage protection which protects the HPCS equipment from a sustained degraded voltage condition. Equipment added by this change includes one additional auxiliary relay, four undervoltage relays, and two timing relays. The existing undervoltage protection on the HPCS bus will become the second level of protection once the design change is implemented. The allowable values proposed for Table 3.3.3-2 reflect a tolerance of 2.8% which is the sum of the maximum tolerance for repeatability and calibration.
The non-accident portion of the change provides a 5 minute time delay setting on the HPCS bus when the bus voltage is at or below 88% when supplied from the off-site power source. During an accident condition (LOCA), a bus undervoltage of 88% and a time delay of 4 seconds will initiate a HPCS system undervoltage alarm in the main control room. The undervoltage signal will J16ATTC86040101 - 1
also cause the auxiliary relay to bypass the timing relay thus tripping breakers No. 4, 5, & 6 which consist of ESF Transformer sources No. 12, 21 and 11 connected to the 4160 volt HPCS bus.
In this case the HPCS bus will be fed from the HPCS diesel generator.
During normal conditions, a bus undervoltage of 88% and a time delay of 4 seconds will initiate a HPCS system undervoltage alarm in the main control rcom and initiate a time delay of 5 minutes. After five minutes of sustained undervoltage, breakers No. 4, 5, & 6 will be tripped and the HPCS bus will be fed from the HPCS diesel generator. During this 5 minutes, if the bus voltage drops below 72%, breakers No. 4, 5, & 6 will be tripped by the existing level of undervoltage protection.
The major loads on the HPCS bus consist of a 4160 volt HPCS motor (E22C001), the 480 volt motor operated valves (M0V's) pump associated with the HPCS system, and the Division 3 battery charger. The HPCS pump motor and 480 volt M0V's have been designed to start at 75% of their nominal voltage. Analyses performed for the HPCS pump motor and 480 volt M0V's have shown that a voltage drop to 72% for 5 minutes is not likely to damage or reduce the life expectancy. The only other equipment connected to the Division 3 bus that could be adversely affected by undervoltage is the Division 3 battery charger which is not affected unless the voltage is less than 85% of nominal voltage; below 85% of nominal voltage the output and input current decrease, but there is not thermal or other damage. In any event, the Division 3 batteries will handle the DC load for at least four hours which provides ample time to identify the problem and apply corrective action to the undervoltage conditions.
The second part of the proposed change provides emergency override protection while the Division 3 Diesel Generator is in the test mode. Presently, if a LOCA occurs while the HPCS diesel generator is' in the test mode, the diesel remains on line in the test mode. This change uses auxiliary relay contacts connected to stationary contacts of the three bus feeder breakers (4, 5, and 6) so that if any of the three breakers are closed and a LOCA occurs, the diesel generator bus feeder breaker is tripped and the diesel generator remains running in standby. If all three feeder breakers (4, 5, and 6) are tripped, the diesel generator stays on line. Incorporation of this design change will permit response to bonafide emergency signals and will return control of the diesel generator to the emergency standby mode. This design feature is incorporated on the Division I and II diesels and is required by position 1 of Regulatory Guide 1.108 (August 1977) as referenced by position 1 of revision 2 of Regulatory Guide 1.9 (December 1979) and Section 5.6.6.2.(1) of IEEE Std. 387-1977. The addition of emergency override to the Division 3 power supply system will be designed using the same criteria used in the Division I and II power systems.
J16ATTC86040101 - 2
SIGNIFICANT HAZARDS CONSIDERATIONS:
The design change associated with this proposed technical specification change provides assurance that the loads connected to the Division 3 bus will trip before possible damage from a sustained undervoltage condition occurs and that the Division 3
. generator returns to the standby mode when an emergency signal is detected.
The proposed change does not involve a significant increare in the probability or consequences of an accident previously evaluated because it adds improvements not currently listed in
.the technical specifications. These proposed changes will enhance the Division 3 power system response to under-voltage conditions and will further ensure readiness of the HPCS Diesel Generator to respond to degraded voltage conditions during a LOCA. Therefore, these changes cannot increase the probability or consequences of an accident.
The proposed change does not create the possibility of a new or different kind of accident from any accident previously evaluated. This change will add a protective means to ensure reliable operation of the Division 3 loads as well as ensuring the Division 3 Diesel Generator is returned to standby and is available for emergency situations. The addition of these protective features does not create the possibility of a new or different kind of accident.
The proposed change does not involve a significant reduction in the margin of safety because the proposed design changes will increase the reliability of the Division 3 power system. The addition of another level of undervoltage protection will increase the margin of safety associated with undervoltage protection of HPCS equipment. The return to standby feature from the test mode will also increase the margin of safety by further ensuring the Division 3 Diesel Generator's capability to respond to accident situations.
Therefore, the proposed changes involve no significant hazards considerations.
J16ATTC86040101 - 3