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Category:OPERATING LICENSES-APPLIATION TO AMEND-RENEW EXISTING
MONTHYEARML20217G6441999-10-13013 October 1999 Application for Amends to Licenses NPF-68 & NPF-81,revising TS to Permit Relaxation of Allowed Bypass Test Times & Completion Times for LCOs 3.3.1 & 3.3.2.Non-proprietary & Proprietary TS & Info Encl.Proprietary Encl Withheld ML20217B1121999-10-0404 October 1999 Application for Amends to Licenses NPF-68 & NPF-81,to Revise TS 5.5.6 Incorporating Exceptions to Reg Guide 1.35,rev 2,as Described in FSAR Section 3.8.1.7.2 ML20212F3521999-09-22022 September 1999 Supplemental Application for Amend to Licenses NPF-68 & NPF-81,proposing Change to SR 3.8.1.13 to Include Upper Limit for DG Loading for 2 H Portion of SR ML20211J5441999-08-30030 August 1999 Application for Amends to Licenses NPF-68 & NPF-81,proposing to Raise Level of Approval Authority for Deviations from Guidelines Provided to Minimize Unit Staff Overtime Specified in TS 5.2.2 ML20211J7211999-08-26026 August 1999 Rev to 990413 Application for Amend to Licenses NPF-68 & NPF-81,updating Versions of LCO 3.0.4 & SR 3.0.4 to Be IAW Versions of LCO 3.0.4 & SR 3.0.4 as They Appear in Rev 1 to NUREG-1431 ML20211E9031999-08-24024 August 1999 Application for Amends to Licenses NPF-68 & NPF-81,relaxing Slave Relay Test Frequency from Quarterly to Refueling Frequency ML20196L3111999-05-18018 May 1999 Application for Amends to Licenses NPF-68 & NPF-81,revising SRs 3.8.1.3 & 3.8.1.13 to Reduce Loading Requirements for DGs ML20206D6831999-04-28028 April 1999 Application for Amends to Licenses NPF-68 & NPF-81,changing Licensing Basis from Present Requirement to Establish Containment Hydrogen Monitoring within 30 Minutes of Initiation of Safety Injection to within 90 Minutes of LOCA ML20205S3731999-04-19019 April 1999 Application for Amends to Licenses NPF-68 & NPF-81,revising SR 3.3.5.2 & Associated Bases to Allow Loss of Voltage & Degraded Voltage Trip Setpoints to Be Treated as Nominal Values in Same Manner as Trip Setpoints for RTS & ESFAS ML20205Q7781999-04-13013 April 1999 Application for Amends to Licenses NPF-68 & NPF-81,updating Versions of LCO 3.0.4 & SR 3.0.4 That Appear in Existing TS to Be Consistent with Versions of LCO 3.0.4 & SR 3.0.4 as in Rev 1 to NUREG-1431 ML20154M9911998-10-15015 October 1998 Application for Amends to Licenses NPF-68 & NPF-81,deleting or Modifying Existing License Conditions Which Have Been Completed or Are No Longer in Effect ML20151U1931998-09-0303 September 1998 Application for Amends to Licenses NPF-68 & NPF-81,changing TS to Support Replacement of Nuclear Instrumentation Sys Short Range & Intermediate Range Channels & post-accident Neutron Flux Monitoring Sys.Ts Pages Encl ML20236R4631998-07-13013 July 1998 Application for Amends to Licenses NPF-68 & NPF-81, Eliminating Periodic Response Time Testing Requirements on Selected Sensors & Selected Protection Channels ML20236F1541998-06-26026 June 1998 Application for Amends to Licenses NPF-68 & NPF-81,revising TS LCO 3.3.6 Re CVI Instrumentation & LCO 3.9.4 Re Containment Penetrations to Facilitate Outage Planning ML20247K4891998-05-15015 May 1998 Suppl Application for Amend to Licenses NPF-78 & NPF-81 Ts. Amend Will Revise New Program 5.5.18 to Extent That Items B,C & D Ref to LCO Action Statement & Revises Bases Insert for New Required Actions B.5.1 & B.5.2 ML20247G9371998-05-0808 May 1998 Application for Amends to Licenses NPF-68 & NPF-81,revising TS 5.5.7, RCP Flywheel Insp Program, by Specifying Alternate Flywheel Insp Once Every Ten Years ML20199A4041998-01-22022 January 1998 Application for Amends to Licenses NPF-68 & NPF-81,adding Conditions for DGs for Extended DG Completion Time of Fourteen Days ML20199G3721997-11-20020 November 1997 Application for Amends to Licenses NPF-68 & NPF-81,proposing Changes That Would Facilitate Treatment of Trip Setpoints as Nominal Values & Correct Certain Typos ML20199J6591997-11-20020 November 1997 Application for Amends to Licenses NPF-68 & NPF-81,revising TS to Change Capacity of Unit 1 Spent Fuel Storage Pool from 288 to 1476 Assemblies & Design Features Description to Reflect Criticality Analyses & Storage Cell Spacing ML20217H8981997-08-0808 August 1997 Revised Application for Amends to Licenses NPF-68 & NPF-81, Revising TS Re Credit for Boron & Enrichment Increase for Fuel Storage ML20141A8121997-06-13013 June 1997 Application for Amends to Licenses NPF-68 & NPF-81,revising TS LCO 3.4.10, Pressurizer Safety Valves, to Reduce Nominal Set Pressure by 1% to 2460 Psig & Increase Tolerance to +2% ML20128G9881996-10-0404 October 1996 Application for Amends to Licenses NPF-68 & NPF-81, Eliminating Credit for Boraflex as Neutron Absorbing Matl in Fuel Storage Pool Criticality Analysis ML20117N6401996-06-17017 June 1996 Application for Amends to Licenses NPF-68 & NPF-81,changing TS Section 5.3.1,allowing Use of Fuel Assemblies Containing Fuel Rods Clad W/Zirlo ML20117N6311996-06-17017 June 1996 Application for Amends to Licenses NPF-68 & NPF-81, Clarifying Requirements of TS SR 4.8.1.1.2.j (2) That Prescribes Pressure Test of Portions of Diesel fuel-oil Sys Designed to Section Iii,Subsection Nd of ASME Code ML20101D4081996-03-0505 March 1996 Application for Amends to Licenses NPF-68 & NPF-81, Converting Existing TS to Improve for Westinghouse Plants as Represented by NUREG-1431 ML20094N3821995-11-20020 November 1995 Rev to 950501 Application for Amends to Licenses NPF-68 & NPF-81,revising TS to Convert Existing TS to Format & Content of NUREG-1431,Westinghouse Improved STS ML20093K2021995-10-16016 October 1995 Application for Amends to Licenses NPF-68 & NPF-81,adding Footnote to Spec 4.6.1.2.d Stating That Type B & C Tests Scheduled for Refueling Outage 1R6 Will Be Conducted Per Option B of 10CFR50 App J ML20098A4801995-09-22022 September 1995 Application for Amends to Licenses NPF-68 & NPF-81, Converting Existing VEGP TS Requirements to Format & Content of NUREG-1431 ML20083M0551995-05-12012 May 1995 Application for Amend to License NPF-68,changing TS SR 4.6.1.2 to Support one-time Exemption from Section III.D.1(a) of 10CFR50,App J,Extending Interval for Type a Test from Scheduled 36 Months to Approx 54 Months ML20082T5591995-05-0101 May 1995 Application for Amends to Licenses NPF-68 & NPF-81, Converting TSs to Improved TSs for Westinghouse Plants as Represented in NUREG-1431 ML20081J4901995-03-17017 March 1995 Application for Amends to Licenses NPF-68 & NPF-81,revising TS 3.9.4 Re Containment Bldg Penetrations,To Allow Personnel Airlock to Be Open During Core Alterations or Movement of Irradiated Fuel within Containment ML20080F7781995-01-20020 January 1995 Application for Amends to Licenses NPF-68 & NPF-81,changing TS 6.4.2 Re Plant Review Board Composition ML20079B1961994-12-29029 December 1994 Application for Amends to Licenses NPF-68 & NPF-81, Requesting to Add Automatic Load Sequencer to Plant ML20079A9411994-12-27027 December 1994 Application for Amends to Licenses NPF-68 & NPF-81,revising Ts,By Revising Leak Test Frequency for Valves W/Resilient Seals ML20077F2131994-12-0606 December 1994 Application for Amends to Licenses NPF-68 & NPF-81, Eliminating Containment Spray Additive Sys ML20073K3761994-10-0303 October 1994 Application for Amends to Licenses NPF-68 & NPF-81,revising TS Reactor Pressure Limits as Results of New Analyses That Account for Nonconservatisms Identified in NRC Info Notice 93-058 & Results of RPV Surveillance Capsule Exams ML20073B7181994-09-13013 September 1994 Application for Amends to Licenses NPF-68 & NPF-81,changing Elimination of Containment Spray Additive Sys ML20072F1981994-08-16016 August 1994 Application for Amend to License NPF-68,eliminating Article 2.C.(6) & Associated Attachment 1 of License Re Diesel Maint & Surveillance ML20072F2151994-08-16016 August 1994 Application for Amends to Licenses NPF-68 & NPF-81,revising TS 3/4.7.1.1 & Bases Re Setpoint Tolerance for Main Steam Safety Valves ML20070A9841994-06-24024 June 1994 Application for Amends to Licenses NPF-68 & NPF-81,revising Values of Z & for Pressurizer Pressure Reactor Trip Instrumentation Trip Setpoints to Allow Use of Alternate Types of Pressure Transmitters ML20069C7271994-05-20020 May 1994 Application for Amends to Licenses NPF-68 & NPF-81, Relocating Heat Flux Channel Factor,Fq(Z),Penalty of 2 Percent in Spec 4.2.2.2.f to cycle-specific COLR to Allow for burnup-dependent Values of Penalty in Excess of 2% ML20070M6711994-04-28028 April 1994 Application for Amends to Licenses NPF-68 & NPF-81,changing TS 3/3.8.1.1, AC Sources Operating, Based on GL 93-05,RG 1.9 & NUMARC 87-00,Rev 1 ML20065F8631994-03-31031 March 1994 Application for Amends to Licenses NPF-68 & NPF-81, Revising TS 3/4.7.1.1 & Bases Re Max Allowed Reactor Thermal Power Operation W/Inoperable Main Steam Safety Valves ML20064L7341994-03-18018 March 1994 Application for Amends to Licenses NPF-68 & NPF-81,proposing Changes to Ts,Incorporating Technical Substance of Corresponding Spec (LCO 3.3.3) from NUREG-1431,Rev 0 ML20064C7181994-03-0101 March 1994 Application for Amends to Licenses NPF-68 & NPF-81, Reinstating Exception 3.0.4 for TS 3.2.4, Quadrant Power Tilt Ratio, ML20063E0591994-02-0303 February 1994 Application for Amends to Licenses NPF-68 & NPF-81, Relocating Requirements of TS 3/4.7.10,area Temp Monitoring to Section 16.3 of FSAR ML20059D2381993-12-30030 December 1993 Application for Amends to Licenses NPF-68 & NPF-81,revising TS to Allow One Time Extension of AOT for RHR Pumps from 3 to 7 Days.One Time Extension Necessary to Allow Mods to RHR Sys While Plant in Mode 1 ML20058A9291993-11-19019 November 1993 Application for Amends to Licenses NPF-68 & NPF-81,proposing Revs to TS Re Dc Sources,Including Rev of SRs of Paragraphs 4.8.2.1.e & F & Table 4.8-2, Battery Srs ML20058A9451993-11-19019 November 1993 Application for Amends to Licenses NPF-68 & NPF-81,adding Footnote to Table 3.3-2,stating That ESFAS Not Required in Mode 2 When AFW Operating to Supply Sfs.Footnote Will Be Applied to Applicable Modes for Functional Unit 6.e ML20058H9971993-11-19019 November 1993 Application for Amends to Licenses NPF-68 & NPF-81, Relocating Requirements of TS 3/4.3.4, Turbine Overspeed Protection to Section 16.3 of Fsar.Ge Proprietary Rept GET-8039 Encl.Proprietary Rept Withheld,Per 10CFR2.790 1999-09-22
[Table view] Category:TEXT-LICENSE APPLICATIONS & PERMITS
MONTHYEARML20217G6441999-10-13013 October 1999 Application for Amends to Licenses NPF-68 & NPF-81,revising TS to Permit Relaxation of Allowed Bypass Test Times & Completion Times for LCOs 3.3.1 & 3.3.2.Non-proprietary & Proprietary TS & Info Encl.Proprietary Encl Withheld ML20217B1121999-10-0404 October 1999 Application for Amends to Licenses NPF-68 & NPF-81,to Revise TS 5.5.6 Incorporating Exceptions to Reg Guide 1.35,rev 2,as Described in FSAR Section 3.8.1.7.2 ML20212F3521999-09-22022 September 1999 Supplemental Application for Amend to Licenses NPF-68 & NPF-81,proposing Change to SR 3.8.1.13 to Include Upper Limit for DG Loading for 2 H Portion of SR ML20211J5441999-08-30030 August 1999 Application for Amends to Licenses NPF-68 & NPF-81,proposing to Raise Level of Approval Authority for Deviations from Guidelines Provided to Minimize Unit Staff Overtime Specified in TS 5.2.2 ML20211J7211999-08-26026 August 1999 Rev to 990413 Application for Amend to Licenses NPF-68 & NPF-81,updating Versions of LCO 3.0.4 & SR 3.0.4 to Be IAW Versions of LCO 3.0.4 & SR 3.0.4 as They Appear in Rev 1 to NUREG-1431 ML20211E9031999-08-24024 August 1999 Application for Amends to Licenses NPF-68 & NPF-81,relaxing Slave Relay Test Frequency from Quarterly to Refueling Frequency ML20196L3111999-05-18018 May 1999 Application for Amends to Licenses NPF-68 & NPF-81,revising SRs 3.8.1.3 & 3.8.1.13 to Reduce Loading Requirements for DGs ML20206D6831999-04-28028 April 1999 Application for Amends to Licenses NPF-68 & NPF-81,changing Licensing Basis from Present Requirement to Establish Containment Hydrogen Monitoring within 30 Minutes of Initiation of Safety Injection to within 90 Minutes of LOCA ML20205S3731999-04-19019 April 1999 Application for Amends to Licenses NPF-68 & NPF-81,revising SR 3.3.5.2 & Associated Bases to Allow Loss of Voltage & Degraded Voltage Trip Setpoints to Be Treated as Nominal Values in Same Manner as Trip Setpoints for RTS & ESFAS ML20205Q7781999-04-13013 April 1999 Application for Amends to Licenses NPF-68 & NPF-81,updating Versions of LCO 3.0.4 & SR 3.0.4 That Appear in Existing TS to Be Consistent with Versions of LCO 3.0.4 & SR 3.0.4 as in Rev 1 to NUREG-1431 ML20154M9911998-10-15015 October 1998 Application for Amends to Licenses NPF-68 & NPF-81,deleting or Modifying Existing License Conditions Which Have Been Completed or Are No Longer in Effect ML20151U1931998-09-0303 September 1998 Application for Amends to Licenses NPF-68 & NPF-81,changing TS to Support Replacement of Nuclear Instrumentation Sys Short Range & Intermediate Range Channels & post-accident Neutron Flux Monitoring Sys.Ts Pages Encl ML20236R4631998-07-13013 July 1998 Application for Amends to Licenses NPF-68 & NPF-81, Eliminating Periodic Response Time Testing Requirements on Selected Sensors & Selected Protection Channels ML20236F1541998-06-26026 June 1998 Application for Amends to Licenses NPF-68 & NPF-81,revising TS LCO 3.3.6 Re CVI Instrumentation & LCO 3.9.4 Re Containment Penetrations to Facilitate Outage Planning ML20247K4891998-05-15015 May 1998 Suppl Application for Amend to Licenses NPF-78 & NPF-81 Ts. Amend Will Revise New Program 5.5.18 to Extent That Items B,C & D Ref to LCO Action Statement & Revises Bases Insert for New Required Actions B.5.1 & B.5.2 ML20247G9371998-05-0808 May 1998 Application for Amends to Licenses NPF-68 & NPF-81,revising TS 5.5.7, RCP Flywheel Insp Program, by Specifying Alternate Flywheel Insp Once Every Ten Years ML20199A4041998-01-22022 January 1998 Application for Amends to Licenses NPF-68 & NPF-81,adding Conditions for DGs for Extended DG Completion Time of Fourteen Days ML20199J6591997-11-20020 November 1997 Application for Amends to Licenses NPF-68 & NPF-81,revising TS to Change Capacity of Unit 1 Spent Fuel Storage Pool from 288 to 1476 Assemblies & Design Features Description to Reflect Criticality Analyses & Storage Cell Spacing ML20199G3721997-11-20020 November 1997 Application for Amends to Licenses NPF-68 & NPF-81,proposing Changes That Would Facilitate Treatment of Trip Setpoints as Nominal Values & Correct Certain Typos ML20217H8981997-08-0808 August 1997 Revised Application for Amends to Licenses NPF-68 & NPF-81, Revising TS Re Credit for Boron & Enrichment Increase for Fuel Storage ML20141A8121997-06-13013 June 1997 Application for Amends to Licenses NPF-68 & NPF-81,revising TS LCO 3.4.10, Pressurizer Safety Valves, to Reduce Nominal Set Pressure by 1% to 2460 Psig & Increase Tolerance to +2% ML20128G9881996-10-0404 October 1996 Application for Amends to Licenses NPF-68 & NPF-81, Eliminating Credit for Boraflex as Neutron Absorbing Matl in Fuel Storage Pool Criticality Analysis ML20117N6401996-06-17017 June 1996 Application for Amends to Licenses NPF-68 & NPF-81,changing TS Section 5.3.1,allowing Use of Fuel Assemblies Containing Fuel Rods Clad W/Zirlo ML20117N6311996-06-17017 June 1996 Application for Amends to Licenses NPF-68 & NPF-81, Clarifying Requirements of TS SR 4.8.1.1.2.j (2) That Prescribes Pressure Test of Portions of Diesel fuel-oil Sys Designed to Section Iii,Subsection Nd of ASME Code ML20101D4081996-03-0505 March 1996 Application for Amends to Licenses NPF-68 & NPF-81, Converting Existing TS to Improve for Westinghouse Plants as Represented by NUREG-1431 ML20094N3821995-11-20020 November 1995 Rev to 950501 Application for Amends to Licenses NPF-68 & NPF-81,revising TS to Convert Existing TS to Format & Content of NUREG-1431,Westinghouse Improved STS ML20093K2021995-10-16016 October 1995 Application for Amends to Licenses NPF-68 & NPF-81,adding Footnote to Spec 4.6.1.2.d Stating That Type B & C Tests Scheduled for Refueling Outage 1R6 Will Be Conducted Per Option B of 10CFR50 App J ML20098A4801995-09-22022 September 1995 Application for Amends to Licenses NPF-68 & NPF-81, Converting Existing VEGP TS Requirements to Format & Content of NUREG-1431 ML20083M0551995-05-12012 May 1995 Application for Amend to License NPF-68,changing TS SR 4.6.1.2 to Support one-time Exemption from Section III.D.1(a) of 10CFR50,App J,Extending Interval for Type a Test from Scheduled 36 Months to Approx 54 Months ML20082T5591995-05-0101 May 1995 Application for Amends to Licenses NPF-68 & NPF-81, Converting TSs to Improved TSs for Westinghouse Plants as Represented in NUREG-1431 ML20081J4901995-03-17017 March 1995 Application for Amends to Licenses NPF-68 & NPF-81,revising TS 3.9.4 Re Containment Bldg Penetrations,To Allow Personnel Airlock to Be Open During Core Alterations or Movement of Irradiated Fuel within Containment ML20080F7781995-01-20020 January 1995 Application for Amends to Licenses NPF-68 & NPF-81,changing TS 6.4.2 Re Plant Review Board Composition ML20079B1961994-12-29029 December 1994 Application for Amends to Licenses NPF-68 & NPF-81, Requesting to Add Automatic Load Sequencer to Plant ML20079A9411994-12-27027 December 1994 Application for Amends to Licenses NPF-68 & NPF-81,revising Ts,By Revising Leak Test Frequency for Valves W/Resilient Seals ML20077F2131994-12-0606 December 1994 Application for Amends to Licenses NPF-68 & NPF-81, Eliminating Containment Spray Additive Sys ML20073K3761994-10-0303 October 1994 Application for Amends to Licenses NPF-68 & NPF-81,revising TS Reactor Pressure Limits as Results of New Analyses That Account for Nonconservatisms Identified in NRC Info Notice 93-058 & Results of RPV Surveillance Capsule Exams ML20073B7181994-09-13013 September 1994 Application for Amends to Licenses NPF-68 & NPF-81,changing Elimination of Containment Spray Additive Sys ML20072F1981994-08-16016 August 1994 Application for Amend to License NPF-68,eliminating Article 2.C.(6) & Associated Attachment 1 of License Re Diesel Maint & Surveillance ML20072F2151994-08-16016 August 1994 Application for Amends to Licenses NPF-68 & NPF-81,revising TS 3/4.7.1.1 & Bases Re Setpoint Tolerance for Main Steam Safety Valves ML20070A9841994-06-24024 June 1994 Application for Amends to Licenses NPF-68 & NPF-81,revising Values of Z & for Pressurizer Pressure Reactor Trip Instrumentation Trip Setpoints to Allow Use of Alternate Types of Pressure Transmitters ML20069C7271994-05-20020 May 1994 Application for Amends to Licenses NPF-68 & NPF-81, Relocating Heat Flux Channel Factor,Fq(Z),Penalty of 2 Percent in Spec 4.2.2.2.f to cycle-specific COLR to Allow for burnup-dependent Values of Penalty in Excess of 2% ML20070M6711994-04-28028 April 1994 Application for Amends to Licenses NPF-68 & NPF-81,changing TS 3/3.8.1.1, AC Sources Operating, Based on GL 93-05,RG 1.9 & NUMARC 87-00,Rev 1 ML20065F8631994-03-31031 March 1994 Application for Amends to Licenses NPF-68 & NPF-81, Revising TS 3/4.7.1.1 & Bases Re Max Allowed Reactor Thermal Power Operation W/Inoperable Main Steam Safety Valves ML20064L7341994-03-18018 March 1994 Application for Amends to Licenses NPF-68 & NPF-81,proposing Changes to Ts,Incorporating Technical Substance of Corresponding Spec (LCO 3.3.3) from NUREG-1431,Rev 0 ML20064C7181994-03-0101 March 1994 Application for Amends to Licenses NPF-68 & NPF-81, Reinstating Exception 3.0.4 for TS 3.2.4, Quadrant Power Tilt Ratio, ML20063E0591994-02-0303 February 1994 Application for Amends to Licenses NPF-68 & NPF-81, Relocating Requirements of TS 3/4.7.10,area Temp Monitoring to Section 16.3 of FSAR ML20059D2381993-12-30030 December 1993 Application for Amends to Licenses NPF-68 & NPF-81,revising TS to Allow One Time Extension of AOT for RHR Pumps from 3 to 7 Days.One Time Extension Necessary to Allow Mods to RHR Sys While Plant in Mode 1 ML20058A9451993-11-19019 November 1993 Application for Amends to Licenses NPF-68 & NPF-81,adding Footnote to Table 3.3-2,stating That ESFAS Not Required in Mode 2 When AFW Operating to Supply Sfs.Footnote Will Be Applied to Applicable Modes for Functional Unit 6.e ML20058A9291993-11-19019 November 1993 Application for Amends to Licenses NPF-68 & NPF-81,proposing Revs to TS Re Dc Sources,Including Rev of SRs of Paragraphs 4.8.2.1.e & F & Table 4.8-2, Battery Srs ML20058H9971993-11-19019 November 1993 Application for Amends to Licenses NPF-68 & NPF-81, Relocating Requirements of TS 3/4.3.4, Turbine Overspeed Protection to Section 16.3 of Fsar.Ge Proprietary Rept GET-8039 Encl.Proprietary Rept Withheld,Per 10CFR2.790 1999-09-22
[Table view] |
Text
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C. K. McCoy we en s m t. , 4 (IC0fgia Power yyy - Vo p, * !!N ' , Ut
- l' % .!'K:!.y5 Wri December 22, 1992 ELV-G1016 i
Docket Nos. 5(M24 5(M25 U. S. Nuclear Regulatory Commission ATfN: Document Control Desk Washington, D. C. 20555 Gentlemen:
VOGTLE ELECITtlC GENERATING PLANT PROPOSED CHANGES TO TECHNICAL SPECIFICATION OUALIFICATION REOUIREMENTS OF TIIE INDEPENDENT SAFETY ENGINEERING GROUP in accordance with the provisions of 10 CFR 50.90, Georgia Power Company (GPC) hereby proposes to amend the Vogtle Electric Generating Plant (VEGP) Unit I and Unit 2 Technical Specifications, Appendix A to Operating Licenses NPF-68 and NPF-81.
The proposed amendment would revise the qualification requirements of the Independent Safety Engineering Group (ISEG). 'Ihe proposed changes and their bases are described in enclosure 1.
An evaluation pursuant to 10 CFR 50.92 showing that the proposed change does not involve a significant hazards consideration is provided in enclosure 2. Instructions for incorporation of the proposed change into the Technical Specifications and a markup of the affected pages are provided as enck>sure 3.
In accordance with 10 CFR 50.91, the designated state official will be sent a copy of this letter and di enclosures.
l E80UUd i! 9212290073 921222 PDR ADOCK 05000424 \ I' P- pga 4'
1: v. .,
I j
'U. S. Nuclear Regulatory Commission -
ELV-01016 F
Page 2 Mr. C. K. McCoy states that he is a Vice President of Georgia Power Company and is authorized to execute this oath on behalf of Georgia Power Company and, that to the best of his-knowledge and belief, the facts in this letter and enclosures are true.
GEORGIA POWER COMPANY By: ~ ~
C. K. hicCoy Sworn to and subscribed before me this B day of 1992.
Amn fL %
Nhtary Public MY 00MMisst0N EXPlRES JANUARY 12,1993 CKM/JMG
Enclosures:
- 1. Basis for Proposed Change 2.10 CFR 50.92 Evaluation
- 3. Instmetions for incorporation and Revised Page C(w): Georgia Power Comoany Mr. W. B. Shipman Mr. M. Sheibani NORMS U. S. Nuclear Regulatory Commission Mr. S. D. Ebneter, Regional Administrator Mr. D. S. Ihxx1, Licensing Project Manager, NRR Mr. B. R. Bonser, Senior Resident Inspector, Vogtle State of Georgia Mr. J. D. Tanner, Commissioner, Department of Natural Resources l.
i I
u , - ._, -
ENCLOSURE 1 VOG'ILE EIECIRIC GENERAllNG PLANT PROPOSED CIIANGES TO TECilNICAL SPECIFICATION OUAUFICATION- ;
REQUIREMENTS OF Tile INDEPENDENT SAFETY ENGINEERING GROUP-l BASIS EOR PROPOSED CIIANGES Proposed Changej The proposeditmendment would revise the qualification requirements for Independent Safety.
Engineering Group (ISEG) members. Currently all ISEG members must have a bachelor's 1
- degree in engineering or related science. Specification 6232 would be revised to allow up to two ISEG members with either (1) a current or previously held Senior Reactor Operator's.
!icense and 5 years of professional level experience in the nuclear field or (2) at least 10 years of professional level experience in his field with at least 5 years of nuclear field experience to be-substituted in lieu of a bachelor's degree.
L L
1 i
l
- El 1
i ENCLOSURE 2 VOGTLE ELECITUC GENERA'UNG PIANT -
PROPOSED CllANGES TO TECIINICAL SPECIFICATION QUALIFICATIOND REQUIREMENTS OF THE INDEPENDENT SAFETY ENGINEERING GROUP 10 CFR 50.92 EVALUATION 4
Pursuant to 10 CFR 50.92, GPC has evaluated the proposed amendment and has detennined that operation of the facility in accordance with the proposed amendment would not involve significant hazards considerations.
Background
NUREG-0737 Section I.B.1.2 requires all applicants for operating licenses to implement an ISEG. As a result of this requirement, with the issuance of the operating license for Vogtle Electric Generating Plant Unit 1, an ISEG was established at VEGP. As required in NUREG-0737, the principal function of the ISEG is to examine plant operating characteristics, NRC issuances, industry advisories and other appropriate sources of plant design and operating-experience information that may indicate areas for improved plant safety. The ISEG is also to -
perform independent review of plant activities including maintenance, operational problems and .
operational an;dysis. Where useful improvements can be achieved, it is expected that this group will develop and present detailed recommendations to corporate management.
Although it could be interpreted that NUREG-0737 did imply that the members of the ISEO should be " engineers," it (nor its listed references of NUREG460 and NUREG494) did not specify any minimum educational qualification requirements for ISEG. It only called for an-
" increase in the avaiLble technical expertise located onsite" and to " provide continuing, systematic, and independent assessment of plant activities" In the spirit of this concept, a more knowledgeable and experienced ISEG group would produce higher quality and useful recommendations fer improvement as emisioned by NUREG-0737.-
Current Technical Specifications prohibit highly trained and' experienced personnel in, for example, the Operations or Operations Support Departments who do not possess a bachelor's degree from being eligible for ISEG consideration even though a significant portion of ISEG evaluations review plant aethities invoMng Operations, Maintenance, and Instrumentation and Control. hs, this change would allow a person with either (1) a current or previously held Senior Reactor Operator's license and 5 years of professional leve.1 experience in the nuclear field or (2) at least 10 years of professional level experience in his field with at least 5 years of nuclear field experience to be substituted in lieu of a bachelor's degree.
1 E2-1 T '-
M9 9 %
s ENCLOSURE 2 (Continued) ;
.VOGTIE ELECTRIC GENERATIb . " 'NT PROPOSED CIIANGES TO TECHNICAL SPECIFK GON OUALIFICATION REQUIREMENE OF TIIE INDEPENDENT SAFIrl Y ENGINEERING GROUP-10 CFR 50.92 EVALUATION De ability to add a person to the Vogtle Electric Generating Plant ISEG staff who has specific ,
nuclear experience would be very valuable by enhancing the ISEG's knowledge level and insight of its evaluations.
The criteria requiring a bachelor's degree used in Vogtle Electric Generating Plant Technical Specification 62.32 stemmed from Section II.D.2.b of NUREG4)731 which stated " Qualification requirements for these individuals sho_uld be at a level generally comparable to that descrit>cd in
- _ Section 42 of ANSI /ANS 3.1 (December 1979 draft), i.e., a bachelor's degree in engineering o with two to four years experience in their field, or equivalent as described in Section 4.1 of ANSI /ANS 3.1." However, Section 4.1 of ANSI /ANS 3.1 (1981) also states that " Individuals who do not Ix>ssess the formal education requirements specified in this section shall not be automatically eliminated where other factors provide sufficient demonstration of their abilities.
These other factors should be evaluated on a case-by-case basis." Vogtle Electric Generating Plant is committed to Regulatory Guide 1.8 (1987), which endorses ANSI /ANS 3.1 (1981).
The level of training and knowledge needed to obtain a Senior Reactor Operator's license is well documented and known. his change would provide the ability of the Vogtle Electric L Generating Plant ISEG to broaden its expertise with direct first-hand operations experience. In
! addition to the Senior Reactor Operator requirement, this change would require 5 years of professional level experience in the nuclear field, which is above the current Vogtle Electric Generating Plant Technical Specification criteria of 2 years experience and is .in accordance with Secdon 4.72 of ANS 3.1 (1981). A second option would ~ substitute 10 years of professional level experience in his field with at least 5 years of which experience shall be in the nuclear field.
These options have already been approved by the NRC for the F:-wer Valley Power Station.
This Technical Specification change would limit the ISEG to a maximum of two such substitutions. This revision will allow an adequate mix of engineering expertise with practical plant experience.
l In summary, this change to Vogtle Electric Generating Plant Technical Specification 6232 l would provide the opportunity to significantly increase the Vogtle Electric Generating Plant ISEG knowiedge level and experience in nuclear power plant operation activities without suffering any discernible reduction in technical knowledge or skills.
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1 ENCLOSURE 2 (Continued) _
VOGTLE ELECTRIC GENERATING PIANT PROPOSED ClIANGES TO TEClINICAL SPECIFICATION OUALIFICATION ,
REQUIREMENTS OF VIE INDEPENDENT SAFETY ENGINEERING GROUP.-
10 CFR 5092 EVALUATION Analysis Georgia Power Company has reviewed the requirements of 10 CFR 50.92 as they relate to the proposed change to section 6.0 of the Technical Specifications and has determined that the change does not involve a significant hazards consideration. In support of this conclusion, the following analysis is provided.
- 1. He proposed change will not significantly increase the probability or consequences of an-accident previously evaluated because the change only addresses qualification requirements of an independent review group and has no change to any plant equipment or structures.
- 2. Dis change does not create the possibility of a new or different kind of accident from any accident previously evaluated. There would be no change to system configurations, plant equipment, or analysis as a result of this proposed amendment.
- 3. He proposed change will not involve a significant reduction in a margin of safety. He proposed revised Technical Specification will substitute appropriate qualification criteria '
for an Independent Review Group and thus will not alter any margin of safety.
Conclusion Based upon the analysis provided herein, Georgia Power Company has determined that the; proposed changes to the Technical Specifications will not significantly increase the probability or . _
consequences of an accident previomly evaluated, create the possibility of a new or different kind of accident from any accident previously evaluated, or involve a significant reduction in a margin of safety. Therefore, the proposed changes do not involve a significant hazards consideration as defined by 10 CFR 50.92 (c).
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