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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Amends to Licenses NPF-68 & NPF-81,deleting or Modifying Existing License Conditions Which Have Been Completed or Are No Longer in Effect ML20151U1931998-09-0303 September 1998 Application for Amends to Licenses NPF-68 & NPF-81,changing TS to Support Replacement of Nuclear Instrumentation Sys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] |
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- s. . ,,,,,m. y ,u August 16, 1994 LCV-0428 Docket Nos. 50-424 50-425 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D. C. 20555 Gentlemen:
VOGTLE ELECTRIC GENERATING PLANT REQUEST TO REVISE OPERATING LICENSE DIESEL MAINTENANCE AND SURVEILLANCE 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 Operating License NPF-68. The proposed revision will eliminan article 2.C.(6) and the associated attachment 1 of the license. Article 2.C.(6) references attachment I which lists special diesel generator (DG) maintenance and surveillance re.luirements.
Concern over the reliability of DGs manufactured by Transamerica Delaval, Inc. (TDI) led to the formation of an owners' group plan for providing an in-depth assessment of the adequacy of TDI DGs of the type utilized by the Vogtle Electric Generating Plant. The NRC staft's evaluation of the owners group program was documented in NUREG-1216.
The NRC included some of the periodic maintenance / surveillance actions described in NUREG-1216 as attachment I to the VEGP Unit 1 operating license. On the basis of operational experience and inspection results, the owners' group provided information to demonstrate that the special concerns of NUREG-1216 are no longer warranted, and that improved DG availability can be achieved without the additional requirements of attachment I to the VEGP Unit I license. The NRC has reviewed the information and has agreed that there is adequate justification for removing the license condition. The basis for this conclusion is documented in Topical Report TDI-EDG-001-A " Basis for Modification to inspection Requirements for Transamerica Delaval, Inc., Emergency Diesel Generators." The removal of the license condition will allow changes to the maintenance and surveillance requirements currently contained in attachment I to the license to be made in accordance with 10 CFR 50.59.
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.. . . ! ., t CJ 9408230244 940816 d PDR ADOCK 0"2000424 P PDR I)
GeorgiaPower A U.S. Nuclear Regulatory Commission PaFe 2 l
Since the NRC has already concurred with the basis for removal of the DG surveillance requirements from the license, Georgia Power Company requests approval of this change by September 1,1994. 1 Enclosure I provides an evaluation pursuant to 10 CFR 50.92 showing that the proposed I changes do not involve significant hazards considerations. Enclosurc 2 contains marked up pages oflicense NPF-68 showing the proposed changes.
In accordance with 10 CFR 50.91, the designated state official will be sent a copy of this letter and all enclosures.
Mr. C. K. McCoy states that he is a vice president of Georgia Power Company and is authorized to execute this oath on behalfof Georgia power company and that, to the best of his knowledge and belief, the facts set forth in this letter and enclosures are true.
4 GEORGIA POWER COMPANY By:
C. K. McCoy Sworri to and subscribed before me this ay of u(/u4f,1994.
"nwn Ad L Notary Public l
l
Enclosures:
- 1. Description of Change and 10 CFR 50.92 Evaluation
- 2. Revised Pages c(w): Georgia Power Compan,y i Mr, J. B. Beasley, Jr. I Mr. M. Sheibani NORMS l j
U. S. Nuc. lear Regulatory Commission Mr. S. D. Ebneter, Regional Administrator Mr. D. S. Ilood, Licensing Project Manager, NRR Mr. B. R. Bonser, Senior Resident Inspector, Vogtle S_ tate _ofGeorgia Mr. J. D. Tanner, Commissioner, Department of Natural Resources 7
,4% -
ENCLOSURE 1 VOGTLE ELECTRIC GENERATING PLANT REQUEST TO REVISE OPERATING LICENSE DIESEL MAINTENANCE AND SURVEILLANCE DESCRIPTION OF CHANGE AND 10 CFR 50.92 EVALUATION Pursuant to 10 CFR 50.92, Georgia Power Company (GPC) has evaluated the proposed revision to the License and has determined that operation of the facility in accordance with the proposed amendment would not involve any significant hazards considerations.
Descriptian The proposed change to the license will eliminate article 2.C.(6) and attachment 1 to the Vogtle Electric Generating Plant Unit I license. Article 2.C.(6) incorporates attachment 1 into the license. Attachment I contains specific surveillance and maintenance conditions imposed by the NRC to address concerns regarding the reliability of Transamerica Delaval, Inc. (TDI) diesel generators (DGs). The proposed change will remove these conditions from the license.
l 3,. ?.
El-1 tr l
i
ENCLOSURE 1(CONTINUED)
VOGTLE ELECTRIC GENERATING PLANT REQUEST TO REVISE OPERATING LICENSE DIESEL MAINTENANCE AND SURVEILLA.NCE D_L3CRIPTION OF CHANGE AND 10 CFR 50.92 EVALUATION Ilagkground Following the crank shaft failure at Shoreham in 1983, Georgia Power Companyjoined with other owners ofTDI DGs to address reliability concerns. The owners' group 2
proposed a two phase program for validation of the DGs. Phase 1 of the program provided sufficient justification for operation of the DGs. The NRC review of phase 1 is documented in NUREG-1216. Some of the specific recommendations of NUREG-1216 were incorporated as prescriptive disassemblies and inspections in appendix 1 of the VEGP Unit I license. It was noted in these findings that many of the conditions were imposed due to a lack of operational experience with these TDI DGs in nuclear standby service. Thousands of hours of operation have been logged by TDI DGs since the j issuance of NUREG-1216, and the reliability of the machines has been demonstrated. In addition, many of the surveillance items that are in place have proven to be as effective as inspections for revealing a potential problem. Using surveillances in lieu ofinspections will also contribute to decreased unavailability of the DGs. Removal of the prescriptive teardown and inspection requirements as license conditions will allow flexibility to determine the best way to monitor engine conditions while maintaining reliability and reducing unavailability. The basis for this conclusion was included in submittals to the l NRC on November 30,1992, and December 7,1993. These two submittals have been I reviewed by the NRC staff and the NRC stafTconcurred with the conclusion as stated in the Safety Evaluation Report (SER) for topical report TDI-EDG-001-A " Basis for Modification to inspection Requirements for Transamerica Delaval, Inc., Emergency Diesel Generators," issued by the NRC on March 17,1994.
Analysis The change to the license will delete license conditions related to DG component inspections that were imposed based on the recommendations in NUREG-1216.
Therefore, the detailed steps of preventive maintenance surveillance programs will become subject to the same degree of NRC stafTreview and approval as for DGs provided by other manufacturers. However, future revisions of the maintenance surveillance program are subject to the provisions of 10 CFR 50.59. The owners group in conjunction with the DG manufacturer is developing a generic DG management program. The transition from the current program to the generic program will be accomplished under the provisions of 10 CFR 50.59.
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ENCLOSURE 1 (CONTINUED)
VOGTLE ELECTRIC GENERATING PLANT REQUEST TO REVISE OPERATING LICENSE DIESEL MAINTENANCE AND SURVEILLANCE DESCRIPTION OF CHANGE AND 10 CFR 50.92 EVALUATION The requirements imposed by attachment I to the license were in addition to the Technical Specifications surveillance and maintenance requirements for DGs in nuclear service. The requirements of attachment I were imposed due to the unresolved concerns about the reliability of TDI DGs that existed at the time ofissuance of the VEGP Unit I license.
Since that time the concerns have been resolved by substantial operational data and inspection results which have demonstrated that these DGs may be treated on a par with other DGs within the nuclear industry and subjected to the same standard regulations without the special requirements of NUREG-1216. The proposed change will result in continuing DG performance in accordance with NRC requirements for this function, and it is likely to result in improved availability. The current Technical Specification surveillance requirements will continue to assure that the DGs are proven at regular intervals to perform in accordance with NRC requirements. These license conditions have been ;
technically justified on the basis ofcurrent reliability data and inspection results of 1 operating TDI DGs throughout the last several years. The NRC staff has agreed with these conclusions as documented in the SER for the topical report.
l The current DG maintenance and surveillance program for the VEGP DGs is in agreement l with the applicable portions of the surveillance and maintenance programs described in the j topical report and with the requirements of the Technical Specifications. Any subsequent '
changes to the surveillance and maintenance requirements currently contained in attachment I to the license following the removal of the attachment from the Operating License will be made in accordance with 10 CFR 50.59.
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l ENCLOSURE 1 (CONTINUED) l VOGTLE ELECTRIC GENERATING PLANT l REQUEST TO REVISE OPERATING LICENSE l DIESEL MAINTENANCE AND SURVEILLANCE I I
DESCRIPTION OF CHANGE AND 10 CFR 50.92 EVALUATION l
CP_u91EN9B Dased on the above considerations, GPC has concluded the following concerning 10 CFR 50.92.
- 1. The proposed change to the license does not involve a significant increase in the probability or consequences of an accident previously evaluated because the ;
availability and reliability of the DGs will remain within the limits previously assumed in the safety analyses.
- 2. The proposed change to the license does not create the possibility of a new or different kind of accident from any accident previously evaluated because it does not result in any physical changes to the plant or in its modes of operation and the DGs have been demonstrated to operate at a level of reliability that is consistent with that which was previously determined to be acceptable for this application.
- 3. The proposed deletion from the license does not involve a significant reduction in a i margin of safety because the results of the operational data and inspection reports have demonstrated that the license conditions are not required to assure that the DGs will be maintained in a state of reliability consistent with that assumed for the safety analyses. ;
Dased upon the preceding information,it has been determined that the proposed change to the license does not involve a significant hazards consideration as dermed by 10 CFR 50.92.
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