|
---|
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Amends to Licenses NPF-68 & NPF-81,deleting or Modifying Existing License Conditions Which Have Been Completed or Are No Longer in Effect ML20151U1931998-09-0303 September 1998 Application for Amends to Licenses NPF-68 & NPF-81,changing TS to Support Replacement of Nuclear Instrumentation Sys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
e . Goorgia Powt Company
.I-
. Ateta Georga30308
!- ,, le6ephone AD4 f.2(,3195
[ IAvhng /ddes 40 Irwerhett Conter Pahay pow OMce Box 1295 l II* W1 May 25, 1990 reuortew oe,*"
W. G. Ha6r6 ton, til Le'nor Vee P#et.ident Near operarons ELV-01713 0402 Docket Nos. 50-424 50-425 U. S. Nuclear Regulatory Commission 4 ATTN: Document Control Desk !
Washington, D. C. 20555
. t Gentlemen: -
V0GTLE ELECTRIC GENERATING PLANT REQUEST TO REVISE TECHNICAL SPECIFICATJON 4.8.1.1.2h(6)(c) ,
In accordance with the provisions of 10 CFR 50.90 and 10 CFR 50.59, Georgia Power Company (GPC) hereby pro)oses to amend the Vogtle Electric Generating +
Plant (VEGP) Units 1 and 2 Tecinical Specifications, Appendix A to Operating Licenses NPF-68 and NPF-81. t Technical Specification (TS) Surveillance Requirement 4.8.1.1.2h(6)(c) requires verification that all automatic diesel generator trips, except engine overspeed, i low lube oil pressure, high jacket water temperature and generator differential are automatically bypassed upon loss of voltage on the emergency bus concurrent I
with a Safety Injection Actuation Signal. The proposed amendment would allow the high jacket water temperature trip to be bypassed to minimize the potential !
for spurious diesel generator trips in the emergency start mode.
The proposed change and its basis are described in Enclosure 1. Our evaluation l
pursuant to to 10 CFR 50.92 showing that the proposed change does not involve t I significant hazards considerations is provided as Enclosure 2. Instructions for L incorporation of the proposed change into the Technical Specifications and a mark-up of the affected page is provided ?s Enclosure 3.
GPC requests that this proposed amendment .:e processed as an emergency Technical '
Specification change. The modification which allows the jacket water high .
temperature trip to be bypassed has become necessary to alleviate a continuing i problem of spurious trips caused by the jacket water temperature switches. GPC :
believes that this modification needs to be made as soon as possible to increase diesel generator reliability.
l l
l
+005300172 900525 I ;
PDR ADOCK 05000424 FI P PDC ,
i !
t
.k
(
,,Gedigb Poner b I
U. S. Nuclear Regulatory Commission i ELV-01713 Paae Two In accordance with 10 CFR 50.91, the designated state official will be sent a copy of this letter and all enclosures.
Mr. W. G. Hairston, 111 states that he is a Senior Vice President of Georgia .,
Power Company and is authorized to execute this oath on behalf of Georgia Power 1 Company and that, to the best of his knowledge and belief, the facts set forth 1 in this letter and enclosures are true.
GEORGIA POWER COMPANY By: Itl. /b d W. G. Hairston, 111 Sworn to and subscribed before me thise5 day of % , 1990.
U b NRAtib Notary Public L WGH,III/NJS/gm (geonstwas>ELW
Enclosures:
- 1. Basis for Proposed Change
- 2. 10 CFR 50.92 Evaluation
- 3. Instructions for Incorporation and Revised Pages l c(w): Georoia Power Company l
Mr. C. K. McCoy
! Mr. G. Bockhold, Jr.
Mr. R. M. Odom
! Mr. P. D. Rushton l NORMS Southern Company Services L Mr. L. B. Long LL, S. Nuclear Reaulatory Commission Mr. S. D. Ebneter, Regional Administrator Mr. T. A. Reed, Licensing Project Manager, NRR Mr. R. F. Aiello, Senior Resident Inspector, Vogtle State of Georoia Mr. J. L. Ledbetter, Commissioner, Department of Natural Resources 4
l ENCLOSURE 1 V0GTLE ELECTRIC GENERATING PLANT RE0 VEST TO REVISE TECHNICAL SPECIFICATION 4.8.1.1.2h(6)(c) r BASIS FOR PROPOSED CHANGE Proposed Chance This proposed change will add a footnote to Specification 4.8.1.1.2h(6)(c) that states "The high jacket water temperature trip may be bypassed." This change wil' allow the diesel generators to be operable with the high jacket water tctper.ture trip bypassed.
Eluill Regulatory Guide 1.9 requires that all diesel generator protective trips except engine overspeed and generator differential be either automatically bypassed -
under accident conditions or implemented with two or more independent measurements for each trip parameter. Sufficient operator reaction time should be available for bypassed trips. The Vogtle Electric Generating Plant diesel generators are designed with two additional trips that are not automatically bypassed. These are the loss of lube oil pressure and high jacket water temperature trips. Plant operating experience has shown that the high jacket water temperature trip system is a source of unnecessary diesel generator trips.
Therefore, GPC is preparing a modification that will allow this trip function '
to be bypassed. In conjunction with this modification it is necessary to modify the Technical Specification to indicate that this trip function may be bypassed.
The effects of this change have been evaluated to determine whether or not it involves any significant hazards consideration. This evaluation is presented ,
in Enclosure 2.
l L
I I
El-1 1
i
,4 I
ENCLOSURE 2 i V0GTLE ELECTRIC GENERATING PLANT I REQUEST TO REVISE TECHNICAL SPECIFICATION 4.8.1.1.2h(6)(c) i 10 CFR 50.92 EVALUATION i Pursuant to 10 CFR 50.92, Georgia Power Company (GPC) has evaluated the attached ,
proposed amendment and has determined that operation of the facility in )
accordance with the proposed amendment would not involve significant hazards I considerations.
BACKGROUND 1 This proposed change is to allow the emergency diesel generators to be started l by an emergency signal with the high jacket water temperature trip bypassed. l This is in addition to the other trips which are already bypassed by an i emergency start signal (Safety Injection (SI), Loss of offsite power (LOSP), or j Emergency Manual start). A modification will be made to add isolation valves in the instrument tubing between the DG high jacket water temperature elenients and the local DG control panel. The valves will normally be closed so that high l Jacket water temperature sensors will not provide input to the engine trip J logic, but may be opened to allow additional engine protection when performing a non-emergency manual start or surveillance of the diesels. In order to close these valves the Technical Specifications are being revised to indicate that the jacket water temperature trip may be bypassed.
- Position 7 of Reg. Guide 1.9, Revision 2, states that all diesel generator protective trips should be either bypassed when the diesel generator is required for a design-basis event or implemented with two or more independent measurements with coincident logic provisions. All protective trips are allowed during periodic testing. The allowed exceptions to the above requirements for bypassing are diesel engine overspeed and generator differential current. -
Currently, all the protective trips except engine overspeed, generator differential, low lube oil pressure', and high jacket water temperature are -
l bypassed during an emergency start. The low lube oil pressure and high jacket i water temperature trips are implemented by three independent measurements for ,
each trip parameter. Actuation of these trips is initiated by two-out-of-three coincident logic. These provisions satisfy the requirements of Position 7 of Reg. Guide 1.9 and, as documented in section 8.3.1 of the SER, were found by the '
NRC to be acceptable.
However, to increase the reliability of the diesel generators, it has now been determined that the trip on high jacket water temperature should also be bypassed during an emergency start. Reg. Guide 1.9, Rev 2 allows this trip to -
i be bypassed under accident conditions provided the operator has sufficient time I to react appropriately to an abnormal diesel-generator condition. In addition, the bypass circuitry should satisfy the requirements of IEEE 279-1971 at the DG system leve? snd should include the capability for (1) testing the status and operability of the bypass circuits, (2) alarming abnormal values of all bypass parameters in the control room, and (3) manually resetting of the trip bypass function. (Capabnity for automatic reset is not acceptable.)
E2-1 l
- : l 1
l
.. i l
ENCLOSURE 2 (CONTINVED) j i
V0GTLE ELECTRIC GENERATING PLANT -l RE0 VEST TO REVISE TECHNICAL SPECIFICATION 4.8.1.1.2h(6)(c) l BACKGROUND (Continued)
This pro)osed change meets the intent of Reg. Guide 1.9. Abnormal values of i high jac cet water temperature will continue to be alarmed locally and in the ;
control room. Low Jacket water pressure is also alarmed. From the time of the ,
high jacket water temperature alarm, the operator will have sufficient time to react appropriately to abnormal diesel generator condition. If the valves are closed, the trips will be bypassed. Operating procedures will assure the i correct position of the valves.
ANALYSIS In order to accomodate the current design, the Technical Specifications require verification that all automatic diesel generator trips are automatically bypassed upon loss of voltage on the emergency bus concurrent with a Safety Injection Actuation signal, except for engine overspeed, generator differential, low lube oil pressure and high jacket water temperature. The proposed Technical Specification change will note that the jacket water temperature trip may be bypassed. The high jacket water temperature trip is designed to protect the diesel generator from a loss of engine cooling. For such an event, the safety function would be provided by the diesel for the other train. During an ,
accident, the advantage of the automatic trip is small relative to the increased reliability achieved by reducing the possibility of a spurious trip.
RESULTS This change will not increase the probability of an accident previously evaluated because it does not affect any of the design basis events that have been previously evaluated in the FSAR. The analyses of cccident consequences do not take credit for the ability to restart a diesel following a diesel generator trip. Therefore, this change will not affect the previously evaluated consequences.
E2-2 1
L 1
l
j . <
ENCLOSURE 2 (CONTINUED) )
l V0GTLE ELECTRIC GENERATING PLANT i RE0 VEST TO REVISE TECHNICAL SPECIFICATION 4.8.1.1.2h(6)(c) ]
10 CFR 50.92 EVALUATION
, RESULTS (Continued)
The revision to the Technical Specification will not create the possiblity of a new or different kind of accident from any accident previously evaluated. No new modes of operation are being imposed on the plant and the diesel generators will continue to perform their function as designed. .
The revision does not result in a significant reduction in the margin of safety provided for events involving a loss of electrical power. The proposed revision will allow the implementation of a modification which is intended to improve the reliability of the diesel generators by minimizing the possibility of spurious trips.
CONCLUSION Based on the preceding analysis, GPC has determined that the proposed change to the Technical Specifications does nnt involve a significant increase in the probability or consequences of an accident previously evaluated, create the j possibility of a new or different kind of accident from any previously evaluated Therefore, GPC
( orconcludes involve a significant that reduction the proposed changein a margin meets of safety. of 10 CFR 50.92(c) and the requirements does not involve significant hazards considerations.
I E2-3
,- - - _ _ - _ _ _ . _ - _ _ - - _ _ - - _ - _ - _ _ _ - - . _ t